ML22174A279

From kanterella
Jump to navigation Jump to search
Notification of NRC Evaluations of Changes, Tests and Experiments Inspection (05000445/2022003 and 05000446/2022003) and Request for Information
ML22174A279
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 06/22/2022
From: Vincent Gaddy
Region 4 Engineering Branch 1
To: Peters K
Vistra Operations Company
References
IR 2022003
Download: ML22174A279 (5)


See also: IR 05000445/2022003

Text

June 22, 2022

Mr. Ken Peters, Senior Vice President

and Chief Nuclear Officer

Attention: Regulatory Affairs

Vistra Operations Company LLC

P.O. Box 1002

Glen Rose, TX 76043

SUBJECT: COMANCHE PEAK NUCLEAR POWER PLANT - NOTIFICATION OF NRC

EVALUATIONS OF CHANGES, TESTS AND EXPERIMENTS INSPECTION

(05000445/2022003 AND 05000446/2022003) AND REQUEST FOR

INFORMATION

Dear Mr. Peters:

The purpose of this letter is to notify you that U.S. Nuclear Regulatory Commission (NRC) staff

will conduct the baseline inspection of changes, tests and experiments at your Comanche Peak

Nuclear Power Plant from September 19 - 23, 2022. The inspection will consist of three reactor

inspectors from the NRCs Region IV office for one week. The inspection will be conducted in

accordance with NRC Inspection Procedure 71111.17T, Evaluations of Changes, Tests and

Experiments, dated December 8, 2016.

Experience has shown that this inspection is resource intensive for both the NRC inspectors

and your staff. To minimize the impact to your onsite resources and to ensure a productive

inspection, we have enclosed a request for information needed for this inspection. Please note

that the documents are requested to be provided by September 6, 2022. Upon review of these

documents, the inspectors will select additional documentation for review upon arrival. It is

important that all documents are up-to-date and complete in order to minimize the number of

additional documents requested during the preparation and/or the onsite portions of the

inspection.

We have discussed the schedule for these inspection activities with your staff and understand

that our regulatory contact for this inspection will be Gary Merka of your Regulatory Affairs

organization. If there are any questions about this inspection or the material requested, please

contact the lead inspector, Gerond A. George, by telephone at 817-200-1562 or by e-mail at

Gerond.George@nrc.gov.

PAPERWORK REDUCTION ACT STATEMENT

This letter contains mandatory information collections that are subject to the Paperwork

Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)

approved these information collections (approval number 3150-0011).

K. Peters 2

Send comments regarding this information collection to the Information Services Branch, Office

of the Chief Information Officer, Mail Stop: T6 A10M, U.S. Nuclear Regulatory Commission,

Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk

Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of

Management and Budget, Washington, DC 20503.

PUBLIC PROTECTION NOTIFICATION

The NRC may not conduct nor 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.

This letter, its enclosure, and your response (if any) will be made available for public inspection

and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document

Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public

Inspections, Exemptions, Requests for Withholding.

Sincerely,

Signed by Gaddy, Vincent

on 06/23/22

Vincent G. Gaddy, Chief

Engineering Branch 1

Division of Reactor Safety

Dockets: 50-445; 50-446

Licenses: NPF-87; NPF-89

Enclosure:

Request for Information

Cc w/ encl: Distribution via LISTSERV

ML22174A279

SUNSI Review ADAMS: Non-Publicly Available Non-Sensitive Keyword:

By: GAG Yes No Publicly Available Sensitive NRC-002

OFFICE DRS/EB1 DRS/EB1

NAME GGeorge VGaddy

SIGNATURE /RA/ /RA/

DATE 6/22/2022 6/22/2022

Request for Information

Evaluations of Changes, Tests and Experiments Inspection

Comanche Peak Nuclear Power Plant

Inspection Report: 05000445/2022003; 05000446/2022003

Inspection Dates: September 19-23, 2022

EPID ID: I-2022-003-0003

Inspection Procedure: IP 71111.17T, Evaluations of Changes, Tests and Experiments

Lead Inspector: Gerond A. George, Senior Reactor Inspector

Information Requested for the In-Office Preparation Week

The following information should be sent to the Region IV office in hard copy or electronic

format (preferred) by September 6, 2022, to the attention of Gerond A. George. We request that

you categorize the documents in your response with the numbered list below. If only hard

copies of the requested documents are available or if the electronic format is too large, please

inform the lead inspector and provide the documents on the first day of the onsite inspection.

Also, the inspectors will select specific items from the information requested below and request

from your staff additional documents needed during the onsite inspection weeks. We ask that

the specific items requested be available and ready for review on the first day of inspection. If

you have any questions regarding this information request, please contact the lead inspector as

soon as possible.

1. A copy of any procedures for conducting 10 CFR 50.59 applicability determinations,

screenings, and evaluations and any other 10 CFR 50.59 program-related documents.

These documents, for example, may include procedures for implementation of alternate

processes or screening criteria such as for replacement part evaluations, design

equivalent changes, long-term configuration control, etc.

2. A list with descriptions of all 10 CFR 50.59 applicability determinations of fully

implemented changes, tests and experiments performed since the last triennial 10 CFR

50.59 inspection that did not result in a screening.

3. A list with descriptions of all 10 CFR 50.59 screenings of fully implemented changes,

tests and experiments performed since the last triennial 10 CFR 50.59 inspection that

did not result in an evaluation.

4. A list with descriptions of all 10 CFR 50.59 evaluations of fully implemented changes,

tests and experiments performed since the last triennial 10 CFR 50.59 inspection that

did not result in an application for a license amendment.

5. A list with descriptions of all fully implemented changes, tests and experiments where an

alternate process or screening criteria was applied since the last triennial 10 CFR 50.59

inspection.

Enclosure

6. A list with descriptions of all temporary plant modifications implemented since the last

triennial 10 CFR 50.59 inspection. Please note whether these temporary modifications

remain in effect.

7. A list with descriptions of all compensatory actions for degraded or non-conforming

conditions implemented since the last triennial 10 CFR 50.59 inspection.

8. A list with descriptions of all normal, abnormal, and emergency operating procedure

changes implemented since the last triennial 10 CFR 50.59 inspection.

9. A list with descriptions of all corrective action documents related to 10 CFR 50.59

applicability determinations, screenings, and evaluations since the last triennial 10 CFR

50.59 inspection.

10. A list including qualification dates of personnel qualified to prepare, review, or approve

10 CFR 50.59 applicability determinations, screenings, and evaluations.

11. A copy of the current updated final safety analysis report, technical specifications, and

technical specification bases.

12. A copy of any self-assessments or audits performed of 10 CFR 50.59 programs since

the last triennial 10 CFR 50.59 inspection.

13. A copy of the most recent submittal of the report containing a brief description of any

changes, tests and experiments, including a summary of the evaluation of each, required

by 10 CFR 50.59(d)(2).

14. A list of systems and system designators and a set of one-line (i.e., simplified) system

diagrams.

Note: Descriptions should be brief but of sufficient detail to ensure that inspectors can

determine the safety and/or risk significance of the screenings, evaluations, and modifications.

Inspector Contact Information:

Gerond A George Jonathan Braisted, Ph.D. Dustin Reinert, Ph.D.

Senior Reactor Inspector Reactor Inspector Reactor Inspector

817-200-1562 817-200-1469 817-200-1534

Gerond.George@nrc.gov Jonathan.Braisted@nrc.gov Dustin.Reinert@nrc.gov

Mailing Address:

U.S. NRC, Region IV

Attn: Gerond A. George

1600 East Lamar Blvd.

Arlington, TX 76011-4125

2