ML103630579

Notification of Inspection (NRC Inspection Report 050-368/2011002) and Request for Information

ML103630579
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/29/2010
From:	Greg Werner NRC/RGN-I/DRS/PSB2
To:	Berryman B Entergy Operations
References
IP 71111.08
Download: ML103630579 (11)

See also: IR 05000368/2011002

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

R E GI ON I V

612 EAST LAMAR BLVD, SUITE 400

ARLINGTON, TEXAS 76011-4125

December 29, 2010

Brad Berryman, Vice President, Operations

Arkansas Nuclear One

Entergy Operations, Inc.

1448 S.R. 333

Russellville, AR 72802

SUBJECT:

ARKANSAS NUCLEAR ONE, UNIT 2 - NOTIFICATION OF INSPECTION (NRC

INSPECTION REPORT 050-368/2011002) AND REQUEST FOR

INFORMATION

Dear Mr. Berryman:

From February 22 to March 5, 2011, reactor inspectors from the Nuclear Regulatory

Commissions (NRC) Region IV office will perform the baseline inservice inspection at Arkansas

Nuclear One, Unit 2, using NRC Inspection Procedure 71111.08, Inservice Inspection

Activities. Experience has shown that this inspection is a resource intensive inspection both for

the NRC inspectors 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), due by February 1, 2011, identifies information to be provided prior to the

inspection to ensure that the inspectors are adequately prepared. The second group (Section B

of the enclosure), identifies the information the inspectors 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. Stephanie Pyle of your licensing

organization. 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 Jim Melfi, lead inspector, at (817) 276-6523 (jim.melfi@nrc.gov) or Dustin

Reinert at (817) 860-8244 (dustin.reinert@nrc.gov).

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.

Entergy Operations, Inc.

- 2 -

In accordance with 10 CFR 2.390 of the NRCs 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 NRCs 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).

Sincerely,

/RA/

Gregory E. Werner, Chief

Plant Support Branch 2

Division of Reactor Safety

Docket: 50-368

License: NPF-06

Enclosure:

Senior Vice President

& Chief Operating Officer

Entergy Operations, Inc.

P.O. Box 31995

Jackson, MS 39286-1995

Thomas Palmisano

Vice President, Oversight

Entergy Operations, Inc.

P.O. Box 31995

Jackson, MS 39286-1995

Mark Giles

Acting Manager, Licensing

Arkansas Nuclear One

1448 SR 333

Russellville, AR 72802

Joseph A. Aluise

Associate General Counsel - Nuclear

Entergy Services, Inc

639 Loyola Avenue

New Orleans, LA 70113

Senior Manager, Nuclear Safety & Licensing

Entergy Nuclear Operations

P.O. Box 31995

Jackson, MS 39286-1995

Entergy Operations, Inc.

- 3 -

Chief, Radiation Control Section

Arkansas Department of Health

4815 West Markham Street, Slot 30

Little Rock, AR 72205-3867

Jim E. Gibson

County Judge of Pope County

100 West Main Street

Russellville, AR 72801

Arkansas Department of Health

Radiation Control Section

4815 West Markham Street, Slot 30

Little Rock, AR 72205-3867

David E. Maxwell, Director

Arkansas Department of Emergency

Management, Bldg. 9501

Camp Joseph T. Robinson

North Little Rock, AR 72199

Chief, Technological Hazards

Branch

FEMA Region VI

800 North Loop 288

Federal Regional Center

Denton, TX 76209

Entergy Operations, Inc.

- 4 -

Electronic distribution by RIV:

Regional Administrator (Elmo.Collins@nrc.gov)

Deputy Regional Administrator (Art.Howell@nrc.gov)

DRP Director (Kriss.Kennedy@nrc.gov)

DRP Deputy Director (Troy.Pruett@nrc.gov)

DRS Director (Anton.Vegel@nrc.gov)

Senior Resident Inspector (Alfred.Sanchez@nrc.gov)

Resident Inspector (Jeff.Rotton@nrc.gov)

Branch Chief, DRP/E (Jeff.Clark@nrc.gov)

Senior Project Engineer, DRP/E (Ray.Azua@nrc.gov)

Project Engineer (Jim.Melfi@nrc.gov)

Project Engineer (William.Schaup@nrc.gov)

Public Affairs Officer (Victor.Dricks@nrc.gov)

Public Affairs Officer (Lara.Uselding@nrc.gov)

Project Manager (Kaly.Kalyanam@nrc.gov)

Branch Chief, DRS/TSB (Michael.Hay@nrc.gov)

RITS Coordinator (Marisa.Herrera@nrc.gov)

Regional Counsel (Karla.Fuller@nrc.gov)

Congressional Affairs Officer (Jenny.Weil@nrc.gov)

OEMail Resource

File located: S:/DRS/REPORTS/reports final/ANO 2011002 RFI-JFM ML 103630579

SUNSI Rev Compl.

7 Yes No

ADAMS

7 Yes No

Reviewer Initials

DRR

Publicly Avail

7 Yes No

Sensitive

Yes 7No

Sens. Type Initials

DRR

EB 1

TSB

C:PSB 2

D. Reinert

J. Melfi

G. Werner

/RA/

/RA/

/RA/

12/20/2010

12/23/2010

12/29/2010

OFFICIAL RECORD COPY

T=Telephone E=E-mail F=Fax

- 1 -

Enclosure

INSERVICE INSPECTION DOCUMENT REQUEST

Inspection Dates:

February 22 through March 5, 2011

Inspection Procedures:

IP 71111.08 Inservice Inspection (ISI) Activities

Inspectors:

Jim Melfi, Project Engineer (Lead Inspector - ISI)

Dustin Reinert, Reactor Inspector

A.

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 (ims.certrec.com preferred), in care of Jim Melfi, by February 1, 2011,

to facilitate the selection of specific items that will be reviewed during the onsite

inspection week. The inspectors will select specific items from the information requested

below and then request from your staff additional documents needed during the onsite

inspection week (Section B of this enclosure). We ask that the specific items selected

from the lists be available and ready for review on the first day of inspection. Please

provide requested documentation electronically, if possible. If requested documents are

large and only hard copy formats are available, please inform the inspectors and provide

subject documentation during the first day of the onsite inspection. If you have any

questions regarding this information request, please call the inspectors as soon as

possible.

A.1

ISI/Welding Programs and Schedule Information

a)

A detailed schedule (including preliminary dates) of:

i)

Nondestructive examinations planned for Class 1 and 2 systems and

containment, performed as part of your ASME,Section XI, risk informed

(if applicable), and augmented inservice inspection programs during the

upcoming outage

Provide a status summary of the nondestructive examination inspection

activities versus the required inspection period percentages for this

interval by category per ASME,Section XI, IWX-2400. Do not provide

separately if other documentation requested contains this information.

ii)

Reactor pressure vessel head examinations planned for the upcoming

outage

iii)

Examinations planned for Alloy 82/182/600 components that are not

included in the Section XI scope, if applicable

iv)

Examinations planned as part of your boric acid corrosion control

program (Mode 3 walkdowns, bolted connection walkdowns, etc.)

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Enclosure

v)

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.

c)

A list of nondestructive examination reports (ultrasonic, radiography, magnetic

particle, dye penetrate, Visual VT-1, VT-2, and VT-3), which have identified

relevant conditions on Code Class 1 and 2 systems since the beginning of the

last refueling outage. This should include the previousSection XI pressure

test(s) conducted during startup and any evaluations associated with the results

of the pressure tests. Also, include in the list the nondestructive examination

reports with relevant conditions in the reactor pressure vessel head penetration

nozzles that have been accepted for continued service. The list of

nondestructive examination reports should include a brief description of the

structures, systems, or components where the relevant condition was identified.

d)

A list with a brief description (e.g., system, material, pipe size, weld number, and

nondestructive examinations performed) of the welds in Code Class 1 and 2

systems which have been fabricated due to component repair/replacement

activities since the beginning of the last refueling outage, or are planned to be

fabricated 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 your 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 the detailed scope of the planned nondestructive examinations of the

reactor vessel head which identifies the types of nondestructive examination

methods to be used on each specific part of the vessel head to fulfill

commitments made in response to NRC Bulletin 2002-02 and

NRC Order EA-03-009. Also, include examination scope expansion criteria and

planned expansion sample sizes if relevant conditions are identified, if applicable.

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Enclosure

b)

A list of the standards and/or requirements that will be used to evaluate

indications identified during nondestructive examination of the reactor vessel

head. (e.g., the specific industry or procedural standards which will be used to

evaluate potential leakage and/or flaw indications).

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.

c)

Please provide a copy of the most recent self-assessment performed for the

boric acid corrosion control program.

A.4

Additional Information Related to all Inservice Inspection Activities

a)

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 Unit 2 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.

b)

Please provide names and phone numbers for the following program leads:

Inservice inspection contacts (examination, planning)

Containment exams

Reactor pressure vessel head exams

Snubbers and supports

Repair and replacement program manager

Licensing contact

Site welding engineer

Boric acid corrosion control program

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Enclosure

B.

Information to be Provided Onsite to the Inspectors at the Entrance Meeting

February 22, 2011

B.1

Inservice Inspection/Welding Programs and Schedule Information

a)

Updated schedules for inservice inspection/nondestructive examination activities,

including steam generator tube inspections, planned welding activities, and

schedule showing contingency repair plans, if available.

b)

For ASME Code Class 1 and 2 welds selected by the inspectors 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 weld procedures used to fabricate the welds

vi)

Copies of procedure qualification records supporting the weld procedures

from B.1.b.v

vii)

Copies of mechanical test reports identified in the procedure qualification

records above

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)

Copies of welder performance qualifications records applicable to the

selected welds, including documentation that welder maintained

proficiency in the applicable welding processes specified in the weld

procedures (at least 6 months prior to the date of subject work)

xii)

Copies of nondestructive examination personnel qualifications (visual

inspection, penetrant testing, ultrasonic testing, radiographic testing), as

applicable

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Enclosure

c)

For the inservice inspection related corrective action issues selected by the

inspectors 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 Code

Class 1 and 2 systems selected by the inspectors 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 inspectors 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

a)

Provide the nondestructive personnel qualification records for the examiners who

will perform examinations of the reactor pressure vessel head.

b)

If a visual examination is planned for the upcoming refueling outage, provide

drawings showing the following:

i)

Reactor pressure vessel head and control rod drive mechanism nozzle

configurations

ii)

Reactor pressure vessel head insulation configuration

The drawings listed above should include fabrication drawings for the nozzle

attachment welds as applicable.

c)

Copy of nondestructive examination reports from the last reactor pressure vessel

head examination.

d)

If a visual examination is planned for the upcoming refueling outage provide a

copy of the evaluation or calculation demonstrating that the scope of the visual

examination of the upper head will meet the 95 percent minimum coverage

required by NRC Order EA-03-009.

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Enclosure

e)

Provide a copy of the procedures that will be used to identify the source of any

boric acid deposits identified on the reactor pressure vessel head. If no explicit

procedures exist which govern this activity, provide a description of the process

to be followed including personnel responsibilities, and expectations.

f)

Provide a copy of the updated calculation of effective degradation years for the

reactor pressure vessel head susceptibility ranking.

g)

Provide a copy of the vendor qualification report(s) that demonstrates the

detection capability of the nondestructive examination equipment used for the

reactor pressure vessel head examinations. Also, identify any changes in

equipment configurations used for the reactor pressure vessel head

examinations which differ from that used in the vendor qualification report(s).

B.3

Boric Acid Corrosion Control Program

a)

Provide boric acid walkdown 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)

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

Codes and Standards

a)

Ready access to (i.e., copies provided to the inspectors 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.

Inspector Contact Information:

Jim Melfi

Dustin Reinert

Project Engineer

Reactor Inspector

817-276-6523

817-860-8244

Jim.Melfi@nrc.gov

Dustin.Reinert@nrc.gov

- 7 -

Enclosure

Mailing Address:

US NRC, Region IV

Attn: Jim Melfi

612 E. Lamar Blvd, Suite 400

Arlington, TX 76011