Text

Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2019001 (DRS-M.Domke)
	ML19024A277
Person / Time
Site:	Point Beach
Issue date:	01/24/2019
From:	Matthew Domke; NRC/RGN-III/DRS/EB1
To:	Craven R; Point Beach
References
	IR 2019001
	Download: ML19024A277 (9)
	v • d • e

January 24, 2019

Mr. Robert Craven

Site Director

NextEra Energy Point Beach, LLC

6610 Nuclear Road

Two Rivers, WI 54241-9516

SUBJECT: POINT BEACH NUCLEAR PLANT, UNIT 1NOTIFICATION OF NRC BASELINE

INSPECTION AND REQUEST FOR INFORMATION; INSPECTION

REPORT 05000266/2019001

Dear Mr. Craven:

The U.S. Nuclear Regulatory Commission (NRC) will soon begin the Baseline Inservice

Inspection Procedure 71111.08. This onsite inspection is scheduled to be performed

March 25, 2019, through April 12, 2019.

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

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

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

These documents have been divided into two groups.

The first group identifies information necessary for inspection preparation. The second group

identifies information the inspector will need upon arrival at the site. It is important that all of

these documents are up-to-date and complete to minimize requests during the preparation

and/or the onsite portions of the inspection.

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

regulatory contact for this inspection will be Ms. Kim Locke, of your organization. If there are

any questions about this inspection or the material requested, please contact the lead inspector

Mr. Matthew Domke at 630-829-9562, or via e-mail at MJD4@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.

R. Craven -2-

This letter and its enclosure 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, Part 2.390, Public Inspections,

Exemptions, Requests for Withholding.

Sincerely,

/RA/

Matthew Domke, Reactor Inspector

Engineering Branch 1

Division of Reactor Safety

Docket No. 50-266

License No. DPR-24

Enclosure:

Document Request for Inservice Inspection

cc: Distribution via LISTSERV

R. Craven -3-

Letter to Robert Craven from Matthew Domke dated January 24, 2019.

SUBJECT: POINT BEACH NUCLEAR PLANT, UNIT 1NOTIFICATION OF NRC BASELINE

INSPECTION AND REQUEST FOR INFORMATION; INSPECTION

REPORT 05000266/2019001

DISTRIBUTION:

Aida Rivera-Varona

RidsNrrDorlLpl3

RidsNrrPMPointBeach

RidsNrrDirsIrib Resource

DRPIII

DRSIII

ADAMS Accession Number: ML19024A277

OFFICE RIII

NAME MDomke:jw

DATE 01/24/19

OFFICIAL RECORD COPY

DOCUMENT REQUEST FOR INSERVICE INSPECTION

Inspection Report: 05000266/2019001

Inspection Dates: March 25, 2019, through April 12, 2019

Inspection Procedures: Inspection Procedure 71111.08, Inservice Inspection

Lead Inspector: Matthew Domke, DRS

630-829-9562

MJD4@nrc.gov

A. Information for the in-office preparation week

The following information is requested by February 25, 2019, to facilitate the selection of

specific items that will be reviewed during the onsite inspection week. The inspector will

select specific items from the information requested below and request a list of additional

documents needed onsite to your staff. The following information is applicable to the

outage Unit 1 unless otherwise indicated. If you have any questions regarding this

information, please call the inspector.

1. For the upcoming outage, a detailed schedule and description of:

a. Non-Destructive Examination (NDE) planned for ASME Class 1 and 2 systems

and containment performed as part of the Inservice Inspection (ISI) program

(please indicate applicable code edition and addenda) and NDEs planned for

other systems including risk-informed, augmented, license renewal, and industry

initiative inspection programs.

b. Reactor vessel upper head examinations required by Title 10 of the Code of

Federal Regulations (CFR), Part 50.55a(g)(6)(ii)(D) and Code Case N-729;

c. Steam generator (SG) tube inspection and repair activities for the upcoming

outage or SG secondary side examinations 1; and

d. Welding on Code Class 1, 2, or 3 components. For each weld examination,

include the weld identification number, description of weld (component name),

category, class, type of exam and procedure number, and date of examination.

1

Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur

and no further information is required for the items identified above requesting SG related information.

Enclosure

DOCUMENT REQUEST FOR INSERVICE INSPECTION

2. A copy of the NDE procedures, SG eddy current examination (ET) acquisition

and analysis procedures, and welding procedures used to perform the activities

identified in Item A.1. For NDE procedures, please include calibration and flaw

characterization/sizing procedures, and, for welding procedures, please include

applicable qualification records with the weld procedure specification. For

ultrasonic examination procedures qualified in accordance with ASME Section XI,

Appendix VIII, provide documentation supporting the procedure qualification

(e.g., the Electric Power Research Institute performance demonstration

qualification summary sheets).

3. A copy of ASME Section XI, Code relief requests applicable to the examinations

identified in Item A.1.

4. A copy of the 10-year ISI Program showing those required exams scheduled to be

performed this outage and those which have been completed.

5. A list identifying NDE reports (ultrasonic, radiography, magnetic particle, or dye

penetrant) which have identified relevant indications on Code Class 1 and 2 systems

since the beginning of the last refueling outage.

6. A list with short description 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. Please identify the system, weld number, and reference

applicable documentation for each (e.g., NIS-2 forms with definitions of system and

component acronyms).

7. If reactor vessel weld examinations required by the ASME Code are scheduled to

occur during the inspection period, provide a detailed description of the welds to be

examined, and the extent of the planned examination.

8. A list of corrective actions initiated since the beginning of the last refueling outage

with description of ISI and SG-related issues such as piping or SG tube degradation

or damage (e.g., cracks, wall thinning, wear, and microbiologically induced corrosion)

or errors identified during piping/SG tube examinations. Also, please include a list of

corrective actions associated with foreign material identified in the reactor vessel,

primary coolant system, SG, or feed systems for the same timeframe.

9. A copy of any 10 CFR 21 reports applicable to your structures, systems, or

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

since the beginning of the last refueling outage.

10. A copy of SG history documentation given to vendors performing ET of the SGs

during the upcoming outage 1.

11. A copy of procedure containing screening criteria used for selecting tubes for in-situ

pressure testing and the procedure to be used for in-situ pressure testing1.

12. A copy of previous outage SG tube operational assessment completed following ET

of the SGs (provide this document even if no SG ET is planned for current outage).

1 Note 1- If no SG examinations are planned for this outage, simply state when the next SG examination will occur.

2

DOCUMENT REQUEST FOR INSERVICE INSPECTION

13. A copy of most recent SG Degradation Assessment (provide this document even if

no SG ET is planned for current outage).

14. A copy of most recent SG Condition Monitoring Assessments1.

15. A copy of the document defining the planned SG ET scope (e.g., 100 percent of

unrepaired tubes with bobbin probe and 20 percent sample of hot leg expansion

transition regions with rotating probe) and identify the scope expansion criteria,

which will be applied. Also identify and describe any deviations in this scope or

expansion criteria from the Electric Power Research Institute Guidelines1.

16. A copy of the document describing the ET acquisition equipment to be applied

including ET probe types. Also identify the extent of planned tube examination

coverage with each probe type (e.g., rotating probe - 0.080 inches, 0.115 inches

pancake coils and mid-range + point coil applied at the top-of-tube-sheet plus

3 inches to minus 12 inches) 1.

17. Provide procedures with guidance/instructions for identifying (e.g., physically locating

the tubes that require repair) and plugging SG tubes 1.

18. Identify and quantify any SG tube leakage experienced during the previous operating

cycle. Also provide documentation identifying which SG was leaking and corrective

actions completed or planned for this condition.

19. Point of contact information (name and site number) for the following activities:

a. ISISite and vendor leads;

b. Boric Acid Inspections and Evaluations;

c. Reactor Vessel Head InspectionSite and vendor leads;

d. SG InspectionSite and vendor leads;

e. Aging Management Programs; and

f. Site Welding Engineer.

B. Onsite information to be provided to the Inspector on the first day of the

inspection (e.g., following the entrance meeting). Please provide hard copies

(e.g., paper records) of the following documents.

1. For welds selected by the inspector from Item A.1.d and A.6 above, provide copies of

the following documents:

a. Document of the weld number and location (e.g., system, train, branch);

b. Document with a detail of the weld construction (e.g., drawing);

1 Note 1- If no SG examinations are planned for this outage, simply state when the next SG examination will occur.

3

DOCUMENT REQUEST FOR INSERVICE INSPECTION

c. Applicable portions of the Design Specification and applicable Code of

Construction for the weldment (e.g., B31.1 or ASME Section III);

d. Applicable Code Edition and Addenda for weld procedure qualification;

e. Applicable weld procedure specifications and weld data sheets used to fabricate

the welds;

f. Copies of procedure qualification records supporting the weld procedure

specifications;

g. Copies of welders performance qualification records;

h. Copies of mechanical test reports identified in the weld procedure qualification

records above;

i. Copies of the nonconformance reports for the selected welds;

j. Access to radiographs and equipment to view radiographs of the selected welds;

k. ASME Code Section XI repair replacement plan and reconciliation for

replacement components/materials;

l. Certified Material Test Reports for replacement pressure boundary materials; and

m. Copies of the NDE required by the construction Code and the pre-service

examination records required by the ASME Code Section XI for the selected

welds.

2. For the ISI-related corrective action issues selected by the inspector from Item A.8

above, provide a copy of the corrective actions and supporting documentation.

3. For the NDE reports with relevant indications on Code Class 1 and 2 Systems

selected by the inspector from Item A.5 above, provide a copy of the examination

records and associated corrective action documents.

4. Updated schedules for Item A.1 (including schedule showing contingency repair

plans if available).

5. Fabrication Drawings (D size) of the reactor vessel welds (including vessel head

J-groove welds), if any are to be examined during the outage. Also provide any

drawings used by NDE vendors to locate these welds.

6. Copy of the procedures which govern the scope, equipment used, and

implementation of the inspections required to identify boric acid leakage from

systems and components above the vessel head.

7. Copy of:

a. Engineering evaluations/assessments of boric acid related deposits and

associated wastage or corrosion for safety significant components; and

4

DOCUMENT REQUEST FOR INSERVICE INSPECTION

b. Corrective action records for coolant leakage including boric acid deposits on

safety-related components identified since the beginning of the last refueling

outage.

8. Copy of the plant procedures used to perform inspections to identify reactor coolant

system leaks or boric acid deposits and the procedures for resolution of leaks or

boric acid deposits.

9. Copy of the documents which demonstrate that the procedures to be used for

volumetric examination of the reactor vessel head penetration J-groove welds were

qualified by a blind demonstration test in accordance with 10 CFR 50.55a(g)(6)(ii)(D).

10. Copy of volumetric, surface and visual examination records for the prior inspection of

the reactor vessel head and head penetration J-groove welds.

11. Provide a copy of the Electric Power Research Institute Examination Technique

Specification Sheets and vendor related documents, which support qualification

of the ET probes to be used during the upcoming SG tube inspections 1.

12. Provide a copy of the guidance to be followed if a loose part or foreign material is

identified in the SGs1.

13. Identify the types of SG tube repair processes, which will be implemented for

defective SG tubes (including any U.S. Nuclear Regulatory Commission

reviews/evaluation/approval of this repair process). Provide the flaw depth

sizing criteria to be applied for ET indications identified in the SG tubes1.

14. Copy of document describing actions to be taken if a new SG tube degradation

mechanism is identified1.

15. Provide document which defines the scope of SG secondary side examinations (if

any are planned) and identify site specific operational history related to degradation

of SG secondary side components (if any).

16. Provide procedures with guidance/instructions for identifying (e.g., physically locating

the tubes that require repair) and plugging SG tubes1.

17. Provide copies of the following standards at the onsite U.S. Nuclear Regulatory

Commission inspection location for the duration of the inspection:

a. Sections V, IX, and XI of the ASME Code with Editions applicable to the ISI

Program and the Repair/Replacement Program;

b. Copy of the performance demonstration initiative (PDI) generic procedures

with the latest applicable revisions that support site qualified ultrasonic

examination of piping welds and components (e.g., PDI-UT-1, PDI-UT-2,

PDI-UT-3, PDI-UT-10 etc.);

1 Note 1- If no SG examinations are planned for this outage, simply indicate when the next SG examination will occur.

5

DOCUMENT REQUEST FOR INSERVICE INSPECTION

c. Electric Power Research Institute and industry standards referenced in the site

procedures used to perform the SG tube ET, which includes Electric Power

Research Institute documents: SG Examination Guidelines, SG Integrity

Assessment Guidelines, SG In-Situ Pressure Test Guidelines 1; and

d. Boric Acid Corrosion Guidebook Revision 1Electric Power Research Institute

Technical Report 1000975.

18. Provide training (e.g., Scaffolding, Fall Protection, Foreign Material Exclusion)

if required to access the non-destructive examinations selected by the inspector

for observation.

If you have questions regarding the information requested, please contact the lead inspector.

1

Note 1- If no SG examinations are planned for this outage, simply indicate when the next SG examination will occur.

6

ML19024A277

Text

Navigation menu

Search