ML19203A012

Request for Information - Inservice Inspection Activities (NRC Inspection Report 05000313/2019004)

ML19203A012
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/16/2019
From:	Wayne Sifre NRC Region 4
To:	Mosher N Entergy Operations
George G
References
Download: ML19203A012 (9)

See also: IR 05000313/2019004

Text

From: Sifre, Wayne

To: "NMosher@Entergy.com" Cc: Loveless, David

George, Gerond

Subject: Request for Information - Unit 1 ISI

Date: Tuesday, July 16, 2019 11:23:00 AM

Natalie, Here is the request for information

as discussed.

Please keep me informed of any changes to outage scope or schedule so that I can adjust accordingly.

Thank you.Wayne Sifre Senior Reactor Inspector 817-200-1193

PAPERWORK REDUCTION ACT STATEMENT

This letter does not contain new or amended information

collection

requirements

subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information

collection

requirements

were approved by the Office of Management

and Budget, Control Number 3150-0011.

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 Office of Management

and Budget control number.In accordance

with 10 CFR 2.390

of the NRC's "Rules of Practice,"

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 NRC's document system (ADAMS).

ADAMS is accessible

from the NRC web site at http://www.nrc.gov/reading

-rm/adams.html

(the Public Electronic

Reading Room)..Information Request

July 16, 2019

Notification of Inspection and Request for Information

Arkansas Nuclear One, Unit 1

NRC Inspection Reports 05000313/2019004 and 05000368/2019004

On October 23, 2019, reactor inspector(s)

from the Nuclear Regulatory

Commission's (NRC)

Region IV office will perform the baseline inservice inspection

at Arkansas Nuclear One, using NRC Inspection

Procedure 71111.08, "Inservice

Inspection

Activities."

Experience

has shown that this inspection

is a resource intensive inspection

both for the NRC inspector(s)

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

inspection, we have enclosed a request for documents needed for this inspection.

These documents have been divided into two groups. The first group (Section A

of the enclosure)

identified

information

to be provided prior to the inspection

to ensure that the inspector(s)

are adequately

prepared.

The second

group (Section B

of the enclosure)

identifies

the information

the inspector(s)

will need upon arrival at the site. It is important that all of these 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 Ms. N. Mosher of your licensing organization.

The tentative inspection

schedule is as follows:

Preparation

week: October 15 - 21, 2019

Onsite weeks: October 23 - 31, 2019 Our inspection

dates are subject to change based on your updated schedule of outage activities.

If there are any questions about this inspection

or the material requested, please contact the lead inspector Wayne Sifre at (817) 200-1193 (Wayne.Sifre@nrc.gov

). A.

Information

to be Provided to the Inspector(s)

for Review during the Preparation

Week (October 15, 2019): A.1 ISI/Welding

Programs and Schedule Information

a. A detailed schedule (including

preliminary

dates) of:

i. Nondestructive

examinations

planned for ASME Code Class Components

performed as part of your ASME Section XI, risk informed (if applicable), and augmented inservice inspection

programs during the upcoming outage.

ii. Examinations

planned for Alloy 82/182/600

components

that are not included in the Section XI scope (If applicable)

iii. Examinations

planned as part of your boric acid corrosion control program (Mode 3 walkdowns, bolted connection

walkdowns, etc.)

iv. Welding activities

that are scheduled to be completed during the upcoming outage (ASME Class 1, 2, or 3 structures, systems, or components)

b. A copy of ASME Section XI Code Relief Requests and associated

NRC safety

evaluations

applicable

to the examinations

identified

above.

i. A list of ASME Code Cases currently being used to include the system and/or component the Code Case is being applied to. c. A list of nondestructive

examination

reports which have identified

recordable

or rejectable

indications

on any ASME Code Class components

since the beginning of the last refueling outage. This should include the previousSection XI pressure test(s) conducted during start up and any evaluations

associated

with the results of the pressure tests. d. A list including a brief description

(e.g., system, code class, weld category, nondestructive

examination

performed)

associated

with the repair/replacement

activities

of any ASME Code Class component since the beginning of the last outage and/or planned this refueling outage. e. If reactor vessel weld examinations

required by the ASME Code are scheduled to occur during the upcoming outage, provide a detailed description

of the welds to be examined and the extent of the planned examination.

Please also provide reference numbers for applicable

procedures

that will be used to conduct these examinations.

f. Copy of any 10 CFR Part 21 reports applicable

to structures, systems, or components

within the scope of Section XI of the ASME Code that have been identified

since the beginning of the last refueling outage. g. A list of any temporary noncode repairs in service (e.g., pinhole leaks). h. Please provide copies of the most recent self-assessments

for the inservice inspection, welding, and Alloy 600 programs A.2 Reactor Pressure Vessel Head a. Provide a detailed scope of the planned bare metal visual examinations

(e.g., volume coverage, limitations, etc.) of the vessel upper head penetrations

and/or any nonvisual nondestructive

examination

of the reactor vessel head

including the examination

procedures

to be used.

i. Provide the records recording the extent of inspection

for each penetration

nozzle including documents which resolved interference

or masking issues that confirm that the extent of examination

meets 10 CFR 50.55a(g)(6)(ii)(D).

ii. Provide records that demonstrate

that a volumetric

or surface leakage path examination

assessment

was performed.

b. Copy of current calculations

for EDY, and RIY as defined in Code Case N-729-1 that establish the volumetric

and visual inspection

frequency for the reactor vessel head and J-groove welds.

A.3 Boric Acid Corrosion Control Program a. Copy of the procedures

that govern the scope, equipment and implementation

of the inspections

required to identify boric acid leakage and the procedures

for boric acid leakage/corrosion

evaluation.

b. Please provide a list of leaks (including

code class of the components)

that have been identified

since the last refueling outage and associated

corrective

action documentation.

If during the last cycle, the unit was shutdown, please provide documentation

of containment

walkdown inspections

performed as part of the boric acid corrosion control program. A.4 Steam Generator Tube Inspections

a. A detailed schedule of steam generator secondary side inspection

activities

for the upcoming outage (if occurring).

A.5 Additional

Information

Related to all Inservice Inspection

Activities

b. A list with a brief description

of inservice inspection, boric acid corrosion control program, and steam generator tube inspection

related issues (e.g., condition reports) entered into your corrective

action program since the beginning of the last refueling outage. For example, a list based upon data base searches using key words related to piping or steam generator tube degradation

such as: inservice inspection, ASME Code,Section XI, NDE, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or errors in

piping/steam

generator tube examinations.

c. Provide training (e.g. Scaffolding, Fall Protection, FME, Confined Space) if they are required for the activities

described in A.1 through A.4. d. Please provide names and phone numbers for the following program leads: Inservice inspection

(examination, planning)Containment

exams Reactor pressure vessel head exams Snubbers and supports Repair and replacement

program Licensing Site welding engineer Boric acid corrosion control program Steam generator inspection

activities

(site lead and vendor contact) B.

Information

to be Provided Onsite to the Inspector(s)

at the Entrance Meeting (October 23, 2019): B.1 Inservice Inspection

/ Welding Programs and Schedule Information

a. Updated schedules for inservice inspection/nondestructive

examination

activities, including planned welding activities, and schedule showing contingency

repair plans, if available.

b. For ASME Code Class welds selected by the inspector(s)

from the lists provided from section A of this enclosure, please provide copies of the following documentation

for each subject weld:

i. Weld data sheet (traveler).

ii. Weld configuration

and system location.

iii. Applicable

Code Edition and Addenda for weldment.

iv. Applicable

Code Edition and Addenda for welding procedures.

v. Applicable

welding procedures

used to fabricate the welds.

vi. Copies of procedure qualification

records (PQRs) supporting

the weld procedures

from B.1.b.v.

vii. Copies of welder's performance

qualification

records (WPQ).

viii. Copies of the nonconformance

reports for the selected welds (If applicable).

ix. Radiographs

of the selected welds and access to equipment to allow viewing radiographs

(if radiographic

testing was performed).

x. Copies of the preservice

examination

records for the selected welds.

xi. Readily accessible

copies of nondestructive

examination

personnel qualifications

records for reviewing.

c. For the inservice inspection

related corrective

action issues selected by the inspector(s)

from section A of this enclosure, provide a copy of the corrective

actions and supporting

documentation.

d. For the nondestructive

examination

reports with relevant conditions

on ASME Code Class components

selected by the inspector(s)

from Section A above, provide a copy of the examination

records, examiner qualification

records, and associated

corrective

action documents.

e. A copy of (or ready access to) most current revision of the inservice inspection

program manual and plan for the current interval. f. For the nondestructive

examinations

selected by the inspector(s)

from section A of this enclosure, provide a copy of the nondestructive

examination

procedures

used to perform the examinations

(including

calibration

and flaw characterization/sizing

procedures).

For ultrasonic

examination

procedures

qualified in accordance

with ASME Code,Section XI, Appendix VIII, provide documentation

supporting

the procedure qualification

(e.g. the EPRI performance

demonstration

qualification

summary sheets). Also, include qualification

documentation

of the specific equipment to be used (e.g., ultrasonic

unit, cables, and transducers

including serial numbers) and nondestructive

examination

personnel qualification

records. B.2 Reactor Pressure Vessel Head (RPVH) Documents requested under Inspection

Procedure 71007, "Reactor Vessel Head Replacement

Inspection."

B.3 Boric Acid Corrosion Control Program a. Please provide boric acid walk down inspection

results, an updated list of boric acid leaks identified

so far this outage, associated

corrective

action documentation, and overall status of planned boric acid inspections.

b. Please provide any engineering

evaluations

completed for boric acid leaks identified

since the end of the last refueling outage. Please include a status of corrective

actions to repair and/or clean these boric acid leaks. Please identify specifically

which known leaks, if any, have remained in service or will remain in service as active leaks. B.4 Steam Generator Tube Inspections

a. Copies of the Examination

Technique Specification

Sheets and associated

justification

for any revisions.

b. Please provide a copy of the eddy current testing procedures

used to perform the steam generator tube inspections

(specifically

calibration

and flaw characterization/sizing

procedures, etc.).

c. Copy of the guidance to be followed if a loose part or foreign material is identified

in the steam generators.

d. Identify the types of SG tube repair processes which will be implemented

for defective SG tubes (including

any NRC reviews/evaluations/approvals

of this repair process).

Provide the flaw depth sizing criteria to be applied for ET indications

identified

in the SG tubes. e. Copy of documents describing

actions to be taken if a new SG tube degradation

mechanism is identified.

f. Provide procedures

with guidance/instructions

for identifying

(e.g. physically

locating the tubes that require plugging) and plugging SG tubes. g. List of corrective

action documents generated by the vendor and/or site with respect to steam generator inspection

activities.

B.5 Codes and Standards a. Ready access to (i.e., copies provided to the inspector(s)

for use during the inspection

at the onsite inspection

location, or room number and location where available):

i. Applicable

Editions of the ASME Code (Sections V, IX, and XI) for the inservice inspection

program and the repair/replacement

program.

ii. EPRI and industry standards referenced

in the procedures

used to perform the steam generator tube eddy current examination.

b. Copy of the performance

demonstration

initiative

(PDI) generic procedures

with the latest applicable

revisions that support site qualified ultrasonic

examinations

of piping welds and components

(e.g., PDI-UT-1, PDI-UT-2, PDI-UT-3, PDI-UT-10, etc.). c. EPRI and industry standard references

in the site procedures

used to perform

the SG tube eddy current examination, which includes EPRI documents:

TR-107621-R1, "Steam Generator Integrity Assessment

Guidelines,"

TR-107620-R1, "Steam Generator In-Situ Pressure Test Guidelines,"

Steam Generator Management

Program: Steam Generator Integrity

Assessment

Guidelines, Part 10, and 1003138, "Pressurized

Water Reactor Steam Generator Examination

Guidelines."

d. Boric Acid Corrosion Guidebook Revision 1 - EPRI Technical Report 1000975.