IR 05000324/2017301
| ML17277A330 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/03/2017 |
| From: | McCoy G J Division of Reactor Safety II |
| To: | Gideon W R Progress Energy Carolinas |
| References | |
| IR 2017301 | |
| Download: ML17277A330 (11) | |
Text
October 3, 2017
William 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 NRC's "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 NRC's 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) 997-4551.
Sincerely,/RA/ Gerald J. McCoy, Chief Operations Branch 1 Division of Reactor Safety Docket Nos.: 50-325, 50-324 License Nos.: DPR-71, DPR-62
Enclosures:
1. Report Details 2. Facility Post-Examination Comments and NRC Resolutions 3. Simulator Fidelity Report cc: Distribution via Listserv
SUBJECT: BRUNSWICK STEAM ELECTRIC PLANT - NRC EXAMINATION REPORT 05000325/2017301 AND 05000324/2017301 Distribution: P. Capehart, RII J. Viera, RII M. Emrich, TTC G. McCoy, RII
PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLE SENSITIVE NON-SENSITIVE ADAMS: Yes ACCESSION NUMBER:__ ___________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS RII:DRS SIGNATURE PGC1 VIA EMAIL JXV3 VIA EMAIL MPE1 VIA EMAIL GJM1 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 OFFICIAL RECORD COPY DOCUMENT NAME: G:\OLEXAMS\BRUNSWICK EXAMINATIONS\INITIAL EXAM 2017-301 (PHIL)\CORRESPONDENCE\BRUNSWICK 2017 301 EXAM REPORT.DOCX Enclosure 1 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
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
OTHER ACTIVITIES
4OA5 Operator Licensing Examinations
a. Inspection Scope
The NRC reviewed the licensee's 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 licensee's post-examination comment may be accessed not earlier than August 8, 2019 in the 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 2
FACILITY POST-EXAMINATION COMMENTS AND NRC RESOLUTIONS
A complete text of the licensee's 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.
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.
External exposure is calculated as follows based on the above equation:
Dose rate is given as 465 mrem/hr
Work time is 25 minutes ATF for PAPRs is 1 465 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 licensee's 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.