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{{Adams
{{Adams
| number = ML18309A350
| number = ML18207A942
| issue date = 11/05/2018
| issue date = 08/01/2018
| title = Notification of NRC Initial Operator Licensing Examination 05000445/2018301 and 05000446/2019301
| title = NRC Examination Report 05000445/2018301, 05000446/2018301
| author name = Gaddy V
| author name = Gaddy V
| author affiliation = NRC/RGN-IV/DRS/OB
| author affiliation = NRC/RGN-IV/DRS/OB
Line 10: Line 10:
| license number = NPF-087, NPF-089
| license number = NPF-087, NPF-089
| contact person =  
| contact person =  
| document type = Letter, License-Operator, Part 55 Examination Related Material
| document report number = 50-445/18-301, 50-446/18-301
| page count = 4
| document type = Letter, License-Operator Examination Report
| page count = 13
}}
}}


Line 17: Line 18:


=Text=
=Text=
{{#Wiki_filter:==SUBJECT:==
{{#Wiki_filter:August 1, 2018
COMANCHE PEAK NUCLEAR POWER PLANT
 
- NOTIFICATION OF NRC INITIAL OPERATOR LICENSING EXAMINATION 05000445/201 9 301 AND 05000446/201 9 301
==SUBJECT:==
COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 - NRC EXAMINATION REPORT 05000 445/2018301; 05000 446/2018301


==Dear Mr. Peters:==
==Dear Mr. Peters:==
In a telephone conversation on October 24, 201 8, between Messrs. J. Ruby , Examination and Simulator Supervisor, and B. Lars on, Chief Examiner, arrangements were made for the administration of licensing examinations at Comanche Peak Nuclear Power Plant during the week of June 10, 201 9. As agreed during the telephone conversation, your staff will prepare the examinations based on the guidelines in Revision 11 to NUREG-1021, "Operator Licensing Examination Standards for Power Reactors
On July 19, 20 18, the U.S. Nuclear Regulatory Commission (NRC) completed an initial operator license examination at Comanche Peak Nuclear Power Plant, Units 1 and 2. The enclosed report documents the examination results and licensing decisions. The preliminary examination results were discussed on June 15, 2018 , with members of your staff.
." The NRC's regional office will discuss with your staff any changes that might be necessary before the examinations are administered.
 
A telephonic exit meeting was conduct ed on July 19, 2018 , with M s. Donna Christiansen, Training Director
, who was provided the NRC licensing decisions.
 
The examination included the evaluation of six applicants for reactor operator licenses, six applicants for instant senior reactor operator licenses, and three applicant s for upgrade senior reactor operator license s. The license examiners determined that fourteen of the fifteen applicants satisfied the requirements of Title 10 of the Code of Federal Regulations (CFR) Part 55, and the appropriate licenses have been issued.
 
There was one post examination comment submitted by your staff.
 
Enclosure 1 contains details of this report and Enclosure 2 summarizes post examination comment resolution
. No violations were identified during this examination
. In accordance with 10 CFR 2.390 of the NRC's "Agency Rules of Practice and Procedure," 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 (PARS) component of UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E. LAMAR BLVD ARLINGTON, TX 76011-4511 NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
 
Sincerely,
/RA/ Vincent G. Gaddy, Chief Operations Branch Division of Reactor Safety Docket Nos.
 
50-445, 50-446 License Nos.
 
NPF-87, NPF-89 Enclosure s: 1. Examination Report 05000445/2018301; 05000446
/2018301
 
===w/Attachment:===
Supplemental Information 2. NRC Post Examination Comment Resolution COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2
- NRC EXAMINATION REPORT 05000445/2018301; 05000 446/2018301 DATED AUGUST 1, 2018 DISTRIBUTION:
KKennedy, RA SMorris, DRA AVegel, DRP MShaffer, DRS JClark, DRS RLantz, DRP DCylkowski, RC JJosey, DRP RKumana, DRP MHaire, DRP RAlexander, DRP AAthar, DRP LNewman, DRP LReyna, DRP JBowen, RIV/OEDO VDricks, ORA JWeil, OCA MO'Banion, NRR AMoreno, RIV/CAO BMaier, RSLO JBridges, OB GGeorge, IPAT PJayroe, DRP/IPAT MHerrera, DRMA R4Enforcement
 
REGION IV Docket Nos.: 50-445, 50-446 License Nos.: NPF-87, NPF-89 Report No s.: 05000445/2018301; 0500044 6/2018301 Licensee: Vistra Operations Company LLC Facility: Comanche Peak Nuclear Power Plant, Units 1 and 2 Location: Glen Rose, Texas Dates: June 11 - July 19 , 201 8 Inspectors:
K. Clayton, Chief Examiner, Senior Operations Engineer J. Kirkland , Senior Operations Engineer C. Osterholtz, Senior Operations Engineer M. Hayes, Operations Engineer Approved By:
Vincent G. Gaddy, Chief Operations Branch Division of Reactor Safety
 
2
 
=SUMMARY=
ER 05000 445/2018301; 05000 446/2018301; June 11 - July 19 , 2018; Comanche Peak Nuclear Power Plant, Units 1 and 2; Initial Operator Licensing Examination Report.
 
NRC examiners evaluated the competency of six applicants for reactor operator licenses, six applicants for instant senior reactor operator licenses and three applicant s for upgrade senior reactor operator license at Comanche Peak Nuclear Power Plant, Units 1 and 2
. The NRC developed the examinations using NUREG
-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 11. The written examination was administered by the licensee on June 20, 2018. NRC examiners administered the operating tests on June 11 - 17, 2018. The examiners determined that fourteen of the fifteen applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued.
 
===A. NRC-Identified and Self-Revealing Findings===
 
None.
 
===B. Licensee-Identified Violations===
 
None.
 
3
 
=REPORT DETAILS=
 
==OTHER ACTIVITIES (OA)==
{{a|4OA5}}
==4OA5 Other Activities (Initial Operator License Examination)==
 
===.1 License Applications===
 
====a. Scope====
NRC examiners reviewed all license application s submitted to ensure each applicant satisfied relevant license eligibility requirements.
 
Examiners also audited three of the license applications in detail to confirm that they accurately reflected the subject applicant's qualifications. This audit focused on the applicant's experience and on
-the-job training, including control manipulations that provided significant reactivity changes.
 
====b. Findings====
No findings were identifie d.
 
===.2 Examination Development===
 
====a. Scope====
The NRC developed the written exam and operating tests in accordance the requirements of NUREG
-1021. The NRC examination team conducted an on
-site validation of the operating tests.
 
====b. Findings====
No findings were identified.
 
===.3 Operator Knowledge and Performance===
 
====a. Scope====
On June 20, 2018, the licensee proctored the administration of the written examinations to all applicants. The licensee staff graded the written examinations, analyzed the results, and presented their analysis and post examination comments to the NRC on June 25, 2018
. The NRC examination team administered the various portions of the operating test s to all applicants on June 11 - 17, 2018.
 
====b. Findings====
No findings were identified.
 
All applicants passed the written examination and fourteen of fifteen applicants passed all portions of the operating test. The final written examination s and post examination analysis and comments may be accessed in the ADAMS system under the accession numbers noted in the attachment.
 
The examination team note d five generic weaknesses associated with applicant performance on the operating tests. All of the weaknesses were attributed to knowledge weaknesses on the topic and included the following items:
1. Several crews (2/4) could not adequately determine a fuel failure event was in progress during a scenario
. 2. Several applicants (3/4) could not adequately operate the control room ventilation system. 3. Applicants had difficulty with anti-pump features of handswitches and their associated breakers
. 4. Several crews (3/4) had difficulty diagnosing a faulted a nd ruptured steam generator during a scenario.
 
5. Several crews struggled with proper communications during the scenario s.
 
The licensee identified five generic weaknesses associated with applicant performance on the written examinations. All of the weaknesses were attributed to knowledge weaknesses on the topic and included the following items:
1. Applicants were unfamiliar with design features of the containment sump
. 2. Applicants were unfamiliar with Abnormal Procedure ABN
-901, Fire Protection System Alarms or Malfunctions
. 3. Applicants had difficulty recalling safety-related battery capacities.
 
4. Applicants were unfamiliar with the immediate operability requirements regarding fuel oil for the emergency diesel generators and their Technical Specification requirements (day tank requirements).


To meet the above schedule, it will be necessary for your staff to furnish the operating test outlines by January 7, 2019. The written examination outlines were provided to your staff on September 18, 2018.
5. Applicants had difficulty determining what system to use during emergency procedures to lower containment hydrogen during a Loss of Coolant Accident
. Copies of all individual examination reports were sent to the facility Training Manager for evaluation and determination of appropriate remedial training.


The written examinations, operating tests, and supporting reference materials identified in Attachment 3 to ES-201 will be due by March 25, 2019. Pursuant to Title 10, Section 55.40(b)(3), of the Code of Federal Regulations (CFR), an authorized representative of the facility licensee shall approve the examinations and tests before they are submitted to the NRC for review and approval. All materials shall be complete and ready-to-use. We request that any personal, proprietary, sensitive unclassified, or Safeguards Information in your response be contained in a separate enclosure and appropriately marked. Delays in receiving the required materials, or the submittal of inadequate or incomplete materials, may cause the examinations to be cancelled or rescheduled. In addition, your support for onsite validation of the examinations is required during the week of May 6, 2019.
The licensee generated Issue Report IR-2018-004425 for resolution of all operating test and written examination generic weaknesses.


To conduct the requested written examinations and operating tests, it will be necessary for your staff to provide adequate space and accommodations in accordance with ES-402, and to make the simulation facility available on the dates noted above. In accordance with ES-302, your staff should retain the original simulator performance data (e.g., system pressures, temperatures, and levels) generated during the dynamic operating tests, along with any video and audio recordings of the dynamic operating tests
===.4 Simulation Facility Performance===
, until the NRC takes licensing action on all the applications and any adjudicatory actions on any hearing demands are complete.


Appendix E to NUREG-1021 contains a number of NRC policies and guidelines that will be in effect while the written examinations and operating tests are being administered.
====a. Scope====
The NRC examiners observed simulator performance with regard to plant fidelity during examination validation and administration.


To permit timely NRC review and evaluation, your staff should submit preliminary reactor operator and senior reactor operator waiver or excusal requests (if any) (Office of Management and Budget (OMB) approval number 3150-0090) at least 60 days before the first examination date (if able). Mr. Larson should be contacted to determine the method for submission of the waiver and/or excusal requests.
====b. Findings====
No findings were identified.


Preliminary reactor operator and senior reactor operator license applications (OMB approval number 3150-0090) and medical certifications (OMB approval number 3150-0024) should be submitted at least 30 days before the first examination date.
===.5 Examination Security===


If the preliminary applications are not received at least 30 days before the examination date, a postponement may be necessary. Final signed applications certifying that all training has been completed and requesting any waivers or excusals, as applicable, should be submitted at least 14 days before the first examination date.
====a. Scope====
The NRC examiners reviewed examination security for examination development during both the onsite preparation week and examination administration week for compliance with 10 CFR 55.49 and NUREG-1021. Plans for simulator security and applicant control were reviewed and discussed with licensee personnel.


Although the minimum guidelines for receiving waiver or excusal requests is 30 days before the first examination date (preliminary) and 14 days before the first examination date (final), the requests should be submitted as early in the process as possible (see the 60-day guideline above). Resolutions resulting from verbal inquiries by the licensee to the NRC are not binding. Submittals addressing waivers and/or excusals should be in writing (i.e., on NRC Form 398, or as directed by Mr. Lars on when contacted to determine the method for submission). The NRC's final decision on whether to grant a waiver or excusal will be documented on the final (not preliminary) NRC Form 398 submitted for the applicant and will not be provided until the final application is submitted to the NRC.
====b. Findings====
No findings were identified.


Paperwork Reduction Act Statement This letter contains information collection requirements that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).
4OA 6 Meetings, Including Exit
These information collections were approved by the Office of Management and Budget, approval number 3150-0018. The burden to the public for these mandatory information collections is estimated to average 400 hours per examination or response, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the information collection.


You may submit comments on any aspect of the information collection, including suggestions for reducing the burden, to FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington , DC 20555-0001, or by electronic mail to INFOCOLLECTS.RESOURCE@NRC.GOV; and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0018), Office of Management and Budget, Washington, DC 20503.
===Exit Meeting Summary===


Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number. In accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Agency Rules of Practice," a copy of this letter and its enclosures will be available electronically for public inspection in the NRC's Agencywide Documents Access and Management System (ADAMS).
The chief examiner presented the preliminary examination results to M r. Thomas McCool, Site Vice President, and other members of the staff on June 15, 2018. A telephonic exit was conducted on July 19, 2018 between Mr. K. Clayton, Chief Examiner, and M s. Donna Christiansen, Training Director
. The licensee did not identify any information or materials used during the examination as proprietary.


ADAMS is accessible from the Electronic Reading Room page of the NRC's public Web Site at http://www.nrc.gov/reading-rm/adams.html
=SUPPLEMENTAL INFORMATION=
. Thank you for your cooperation in this matter. Mr. Ruby has been advised of the policies and guidelines referenced in this letter. If you have any questions regarding the NRC's examination procedures and guidelines, please contact Mr. Lars on at 817-200-1 1 72 or myself at 817-200-1159.


Sincerely,
==KEY POINTS OF CONTACT==
/RA/ Vincent G. Gaddy, Chief Operations Branch Division of Reactor Safety Dockets: 50-445; 50-446 Licenses: NPF-87; NPF-89 cc: Electronic Distribution
 
===Licensee Personnel===
: [[contact::T. McCool]], Site Vice President
: [[contact::D. Christiansen]], Training Director
: [[contact::J. Lloyd]], Operations Support Manager
: [[contact::J. Ruby]], Exam Developer
 
===NRC Personnel===
: [[contact::J. Josey]], Senior Resident Inspector
 
==ADAMS DOCUMENTS REFERENCED==


ML18309A350 SUNSI Review:
ADAMS: Non-Publicly Available Non-Sensitive Keyword: By: VGaddy Yes No Publicly Available Sensitive NRC-002 OFFICE SOE:OB C:OB NAME BLarson VGaddy SIGNATURE /RA/ /RA/ DATE 11/05/18 11/05/18
}}
}}

Revision as of 00:38, 17 June 2019

NRC Examination Report 05000445/2018301, 05000446/2018301
ML18207A942
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 08/01/2018
From: Vincent Gaddy
Operations Branch IV
To: Peters K
Vistra Operations Company
References
50-445/18-301, 50-446/18-301
Download: ML18207A942 (13)
v • d • e


Text

August 1, 2018

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 - NRC EXAMINATION REPORT 05000 445/2018301; 05000 446/2018301

Dear Mr. Peters:

On July 19, 20 18, the U.S. Nuclear Regulatory Commission (NRC) completed an initial operator license examination at Comanche Peak Nuclear Power Plant, Units 1 and 2. The enclosed report documents the examination results and licensing decisions. The preliminary examination results were discussed on June 15, 2018 , with members of your staff.

A telephonic exit meeting was conduct ed on July 19, 2018 , with M s. Donna Christiansen, Training Director

, who was provided the NRC licensing decisions.

The examination included the evaluation of six applicants for reactor operator licenses, six applicants for instant senior reactor operator licenses, and three applicant s for upgrade senior reactor operator license s. The license examiners determined that fourteen of the fifteen applicants satisfied the requirements of Title 10 of the Code of Federal Regulations (CFR) Part 55, and the appropriate licenses have been issued.

There was one post examination comment submitted by your staff.

Enclosure 1 contains details of this report and Enclosure 2 summarizes post examination comment resolution

. No violations were identified during this examination

. In accordance with 10 CFR 2.390 of the NRC's "Agency Rules of Practice and Procedure," 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 (PARS) component of UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E. LAMAR BLVD ARLINGTON, TX 76011-4511 NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/ Vincent G. Gaddy, Chief Operations Branch Division of Reactor Safety Docket Nos.

50-445, 50-446 License Nos.

NPF-87, NPF-89 Enclosure s: 1. Examination Report 05000445/2018301; 05000446

/2018301

w/Attachment:

Supplemental Information 2. NRC Post Examination Comment Resolution COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2

- NRC EXAMINATION REPORT 05000445/2018301; 05000 446/2018301 DATED AUGUST 1, 2018 DISTRIBUTION:

KKennedy, RA SMorris, DRA AVegel, DRP MShaffer, DRS JClark, DRS RLantz, DRP DCylkowski, RC JJosey, DRP RKumana, DRP MHaire, DRP RAlexander, DRP AAthar, DRP LNewman, DRP LReyna, DRP JBowen, RIV/OEDO VDricks, ORA JWeil, OCA MO'Banion, NRR AMoreno, RIV/CAO BMaier, RSLO JBridges, OB GGeorge, IPAT PJayroe, DRP/IPAT MHerrera, DRMA R4Enforcement

REGION IV Docket Nos.: 50-445, 50-446 License Nos.: NPF-87, NPF-89 Report No s.: 05000445/2018301; 0500044 6/2018301 Licensee: Vistra Operations Company LLC Facility: Comanche Peak Nuclear Power Plant, Units 1 and 2 Location: Glen Rose, Texas Dates: June 11 - July 19 , 201 8 Inspectors:

K. Clayton, Chief Examiner, Senior Operations Engineer J. Kirkland , Senior Operations Engineer C. Osterholtz, Senior Operations Engineer M. Hayes, Operations Engineer Approved By:

Vincent G. Gaddy, Chief Operations Branch Division of Reactor Safety

2

SUMMARY

ER 05000 445/2018301; 05000 446/2018301; June 11 - July 19 , 2018; Comanche Peak Nuclear Power Plant, Units 1 and 2; Initial Operator Licensing Examination Report.

NRC examiners evaluated the competency of six applicants for reactor operator licenses, six applicants for instant senior reactor operator licenses and three applicant s for upgrade senior reactor operator license at Comanche Peak Nuclear Power Plant, Units 1 and 2

. The NRC developed the examinations using NUREG

-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 11. The written examination was administered by the licensee on June 20, 2018. NRC examiners administered the operating tests on June 11 - 17, 2018. The examiners determined that fourteen of the fifteen applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued.

A. NRC-Identified and Self-Revealing Findings

None.

B. Licensee-Identified Violations

None.

3

REPORT DETAILS

OTHER ACTIVITIES (OA)

4OA5 Other Activities (Initial Operator License Examination)

.1 License Applications

a. Scope

NRC examiners reviewed all license application s submitted to ensure each applicant satisfied relevant license eligibility requirements.

Examiners also audited three of the license applications in detail to confirm that they accurately reflected the subject applicant's qualifications. This audit focused on the applicant's experience and on

-the-job training, including control manipulations that provided significant reactivity changes.

b. Findings

No findings were identifie d.

.2 Examination Development

a. Scope

The NRC developed the written exam and operating tests in accordance the requirements of NUREG

-1021. The NRC examination team conducted an on

-site validation of the operating tests.

b. Findings

No findings were identified.

.3 Operator Knowledge and Performance

a. Scope

On June 20, 2018, the licensee proctored the administration of the written examinations to all applicants. The licensee staff graded the written examinations, analyzed the results, and presented their analysis and post examination comments to the NRC on June 25, 2018

. The NRC examination team administered the various portions of the operating test s to all applicants on June 11 - 17, 2018.

b. Findings

No findings were identified.

All applicants passed the written examination and fourteen of fifteen applicants passed all portions of the operating test. The final written examination s and post examination analysis and comments may be accessed in the ADAMS system under the accession numbers noted in the attachment.

The examination team note d five generic weaknesses associated with applicant performance on the operating tests. All of the weaknesses were attributed to knowledge weaknesses on the topic and included the following items:

1. Several crews (2/4) could not adequately determine a fuel failure event was in progress during a scenario

. 2. Several applicants (3/4) could not adequately operate the control room ventilation system. 3. Applicants had difficulty with anti-pump features of handswitches and their associated breakers

. 4. Several crews (3/4) had difficulty diagnosing a faulted a nd ruptured steam generator during a scenario.

5. Several crews struggled with proper communications during the scenario s.

The licensee identified five generic weaknesses associated with applicant performance on the written examinations. All of the weaknesses were attributed to knowledge weaknesses on the topic and included the following items:

1. Applicants were unfamiliar with design features of the containment sump

. 2. Applicants were unfamiliar with Abnormal Procedure ABN

-901, Fire Protection System Alarms or Malfunctions

. 3. Applicants had difficulty recalling safety-related battery capacities.

4. Applicants were unfamiliar with the immediate operability requirements regarding fuel oil for the emergency diesel generators and their Technical Specification requirements (day tank requirements).

5. Applicants had difficulty determining what system to use during emergency procedures to lower containment hydrogen during a Loss of Coolant Accident

. Copies of all individual examination reports were sent to the facility Training Manager for evaluation and determination of appropriate remedial training.

The licensee generated Issue Report IR-2018-004425 for resolution of all operating test and written examination generic weaknesses.

.4 Simulation Facility Performance

a. Scope

The NRC examiners observed simulator performance with regard to plant fidelity during examination validation and administration.

b. Findings

No findings were identified.

.5 Examination Security

a. Scope

The NRC examiners reviewed examination security for examination development during both the onsite preparation week and examination administration week for compliance with 10 CFR 55.49 and NUREG-1021. Plans for simulator security and applicant control were reviewed and discussed with licensee personnel.

b. Findings

No findings were identified.

4OA 6 Meetings, Including Exit

Exit Meeting Summary

The chief examiner presented the preliminary examination results to M r. Thomas McCool, Site Vice President, and other members of the staff on June 15, 2018. A telephonic exit was conducted on July 19, 2018 between Mr. K. Clayton, Chief Examiner, and M s. Donna Christiansen, Training Director

. The licensee did not identify any information or materials used during the examination as proprietary.

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

T. McCool, Site Vice President
D. Christiansen, Training Director
J. Lloyd, Operations Support Manager
J. Ruby, Exam Developer

NRC Personnel

J. Josey, Senior Resident Inspector

ADAMS DOCUMENTS REFERENCED

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