ML17277A330
| ML17277A330 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/03/2017 |
| From: | Gerald Mccoy Division of Reactor Safety II |
| To: | William Gideon Progress Energy Carolinas |
| References | |
| IR 2017301 | |
| Download: ML17277A330 (11) | |
See also: IR 05000324/2017301
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
October 3, 2017
William R. Gideon
Site Vice President
Brunswick Steam Electric Plant
8470 River Road, SE (M/C BNP001)
Southport, NC 28461
SUBJECT: BRUNSWICK STEAM ELECTRIC PLANT - NRC EXAMINATION REPORT
05000325/2017301 AND 05000324/2017301
Dear Mr. Gideon:
During the period July 24 through August 1, 2017, the Nuclear Regulatory Commission (NRC)
administered operating tests to employees of your company who had applied for licenses to
operate Brunswick Steam Electric Plant. At the conclusion of the tests, the examiners
discussed preliminary findings related to the operating tests and the written examination
submittal with those members of your staff identified in the enclosed report. The written
examination was administered by your staff on August 8, 2017.
Seven Reactor Operator (RO) and five Senior Reactor Operator (SRO) applicants passed both
the operating test and written examination. One SRO applicant passed the written examination
while the operating test was waived. One SRO applicant failed the scenario portion of the
examination. There was one JPM post-examination comment. Thirteen applicants were issued
licenses commensurate with the level of examination administered. A Simulator Fidelity Report
is included in this report as Enclosure 3.
All examination changes agreed upon between the NRC and your staff were made according to
NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 10.
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).
W. Gideon 2
If you have any questions concerning this letter, please contact me at (404) 997-4551.
Sincerely,
/RA/
Gerald J. McCoy, Chief
Operations Branch 1
Division of Reactor Safety
Docket Nos.: 50-325, 50-324
Enclosures:
1. Report Details
2. Facility Post-Examination Comments
and NRC Resolutions
3. Simulator Fidelity Report
cc: Distribution via Listserv
__ ___________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED
OFFICE RII:DRS RII:DRS RII:DRS RII:DRS
SIGNATURE PGC1 VIA JXV3 VIA MPE1 VIA GJM1
EMAIL EMAIL EMAIL
NAME PCAPEHART JVIERA MEMRICH GMCCOY
DATE 9/28/2017 10/02/2017 9/28/2017 10/3 /2017
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
U.S. NUCLEAR REGULATORY COMMISSION
REGION II
Docket No.: 50-325, 50-324
Report No.: 05000325/2017301, 05000324/2017301
Licensee: Duke Energy Progress, Inc.
Facility: Brunswick Steam Electric Plant, Units 1 and 2
Location: Southport, NC
Dates: Operating Test - July 24 through August 1, 2017
Written Examination - August 8, 2017
Examiners: Phillip Capehart, Chief Examiner, Senior Operations Engineer
Joe Viera, Operations Engineer
Matthew Emrich, Senior Reactor Technology Instructor
Approved by: Gerald J. McCoy, Chief
Operations Branch 1
Division of Reactor Safety
Enclosure 1
SUMMARY
ER 05000325/2017301, 05000324/2017301; operating test July 24 through August 1, 2017 &
written exam August 8, 2017; Brunswick Steam Electric Plant, Units 1 and 2; Operator License
Examinations.
Nuclear Regulatory Commission (NRC) examiners conducted an initial examination in
accordance with the guidelines in Revision 10 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.
The operating tests and written examinations were developed by the NRC.
The NRC administered the operating tests during the period July 24 through August 1, 2017.
Members of the Brunswick Steam Electric Plant training staff administered the written
examination on August 8, 2017. Seven Reactor Operator (RO) and five Senior Reactor
Operator (SRO) applicants passed both the operating test and written examination. One SRO
passed the written examination while the operating test was waived. One SRO applicant failed
the simulator scenario portion of the examination. Thirteen applicants were issued licenses
commensurate with the level of examination administered.
There was one JPM post-examination comment.
No findings were identified.
REPORT DETAILS
4. OTHER ACTIVITIES
4OA5 Operator Licensing Examinations
a. Inspection Scope
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 administered the operating tests during the period July 24 through August 1,
2017. The NRC examiners evaluated seven Reactor Operator (RO) and six Senior
Reactor Operator (SRO) applicants using the guidelines contained in NUREG-1021.
Members of the Brunswick Steam Electric Plant training staff administered the written
examination on August 8, 2017 to seven SRO applicants and seven RO applicant.
Evaluations of applicants and reviews of associated documentation were performed to
determine if the applicants, who applied for licenses to operate the Brunswick Steam
Electric Plant, met the requirements specified in 10 CFR Part 55, Operators Licenses.
The NRC evaluated the performance and fidelity of the simulation facility during the
preparation and conduct of the operating tests.
b. Findings
No findings were identified.
The NRC developed the written examination sample plan outline, the written
examination, and the operating test. All examination material was developed in
accordance with the guidelines contained in Revision 10 of NUREG-1021. The licensee
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.
Seven Reactor Operator (RO) and five Senior Reactor Operator (SRO) applicants
passed both the operating test and written examination. One SRO passed the written
examination while the operating test was waived. One SRO applicant failed the
simulator scenario portion of the examination.Twelve applicants passed both the
operating test and written examination and one applicant passed the written examination
while the operating test was waived. Seven RO and six SRO applicants 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 one post-examination comment concerning an administrative
JPM on the operating portion of the examination. A copy of the final RO and SRO
written examinations and answer keys, with all changes incorporated, and the licensees
post-examination comment may be accessed not earlier than August 8, 2019 in the
4
ADAMS system (ADAMS Accession Numbers ML17263A601, ML17263A604, and
ML17263A622, respectively).
4OA6 Meetings, Including Exit
Exit Meeting Summary
On August 1, 2017, the NRC examination team discussed generic issues associated
with the operating test with Karl Moser, Plant General Manager, and members of the
Brunswick Steam Electric Plant staff. The examiners asked the licensee if any of the
examination material was proprietary, or if any of the examination material received
should be withheld from public disclosure. No proprietary information was identified.
KEY POINTS OF CONTACT
Licensee personnel
Karl Moser, Plant Manager
Kurt Kruger, Nuclear Operations Manager
Jon Hicks, Nuclear Training Manager
Bryan Wooten, Nuclear Organizational Effectiveness Director
Andy Padleckas, Assistant Operations Manager, Support
Mark Similey, Nuclear Operations Training Manager
Ed Rau, Nuclear Operations Training Supervisor
James Buckingham, Nuclear Operations Training Supervisor
John Miller, Assistant Operations Training Manager
Craig Oliver, Nuclear Control Room Supervisor
Lee Grzeck, Nuclear Regulatory Affairs Manager
Michael Braden, Senior Nuclear Engineer
Mike Gibson, Nuclear Operations Training Instructor
Brian Stetson, Nuclear Operations Training Instructor
Josh Ashcroft, Nuclear Operations Training Instructor
FACILITY POST-EXAMINATION COMMENTS AND NRC RESOLUTIONS
A complete text of the licensees post-examination comments can be found in ADAMS under
Accession Number ML17263A622.
Item
Admin JPM: RC-1 determining TEDE while working in a High Airborne Area.
Comment:
The licensee commented that the standard for step 2 and step 4 was inadequate.
Below is the explanation for step 2 and step 4 of RC-1
Step 2 - Determine internal dose while wearing a respirator.
STANDARD-Internal dose with respirator determined to be 0 mrem
Explanation:
For step two, internal exposure is assumed to be zero based on using a powered air purifying respirator which
due to positive pressure is assumed to allow no internal exposure.
However, if using AD-RP-ALL-2019, to calculate internal dose it would actually be calculated to be .0521 mrem.
Below is an explanation of how to determine this value.
Given in the stem is a weighted DAC of 50.
IAW attachment 3 step 4 this weighted DAC is the equivalent of all the individual respective nuclide DAC
values.
This weighted DAC of 50 is then used in the following equation from attachment 3 step 7b to calculate
DAC-hours for internal dose.
Enclosure 2
2
The respirator protection factor is 1000 for all duke PAPRs based on attachment 1 note 7
The exposure time is 25 minutes which is given in the initial conditions.
Therefore the equation is solved as follows:
DAC-Hours= [(50/1000) x 25/60]
DAC-Hours= .0208
Internal Dose = DAC-Hours x 2.5
Internal Dose=.0208 x 2.5
Internal dose=.0521 mrem
This internal does of .0521 mrem is ~0.
Step 4 - Determine total exposure while wearing a respirator.
STANDARD-Total dose with respirator determined to be 193.8 mrem (Acceptable range is 193. 7
mrem to 195.3 mrem). (see key)
Explanation:
Total dose is the sum of external exposure and internal exposure. This total dose can be solved using
AD-RP-ALL-2019 Attachment 2.
3
External exposure is calculated as follows based on the above equation:
Dose rate is given as 465 mrem/hr
Work time is 25 minutes
465 x (25/60) x 1 =193.7 to 195.3 mrem
Therefore external exposure=193.7 to 195.3 mrem
Internal exposure was calculated above in step 2 as either 0 or .0521 mrem.
Total exposure is (193.7 to 195.3 mrem external dose) + (0 to .0521 mrem internal dose)
Therefore total exposure= 193.7 mrem to 195.821 mrem.
NRC Resolution
The licensees recommendation was accepted.
The NRC agrees with the new standard as determined by the licensee and incorporated the
new standards into the final revision of the JPM.
The JPM has been changed to reflect the new standards for step 2 and step 4.
SIMULATOR FIDELITY REPORT
Facility Licensee: Brunswick Steam Electric Plant
Facility Docket No.: 05000325, 05000324
Operating Test Administered: July 24- August 1, 2017
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.
No simulator fidelity or configuration issues were identified.
Enclosure 3