ML19024A277

Ltr 01/24/19 Point Beach Nuclear Plant, Unit 1 - 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)

See also: IR 05000266/2019001

Text

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 1-NOTIFICATION OF NRC BASELINE INSPECTION AND REQUEST FOR

INFORMATION; INSPECTION REPORT 05000 266/20 19 00 1 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. Matt hew 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/ Matt hew 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 2 4, 2019. SUBJECT: POINT BEACH NUCLEAR PLANT, UNIT 1

-NOTIFICATION OF NRC BASELINE INSPECTION AND REQUEST FOR

INFORMATION; INSPECTION REPORT 05000266/20 19 00 1 DISTRIBUTION

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Darrell Roberts

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Jamnes Cameron

Allan Barker

DRPIII DRSIII ADAMS Accession Number: ML19024A277

OFFICE RIII NAME MDomke:jw DATE 0 1/24/19 OFFICIAL RECORD COPY

DOCUMENT REQUEST FOR INSERVICE INSPECTION

Enclosure Inspection Report

05000 266/20 19 00 1 Inspection

Dates: March 25, 2019

, through April 12, 2019

Inspection

Procedures

Inspection Procedure 71111.08, Inservice Inspection

Lead Inspector

Matt hew Domke, DRS 630-829-9562 MJD4@nrc.gov

A. Information for the

i n-office preparation

w eek 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 (IS I) program (please indicate applicable code edition and

addenda) and NDE s 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.

DOCUMENT REQUEST FOR INSERVICE INSPECTION

2 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 an

d 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 testing

1. 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.

DOCUMENT REQUEST FOR INSERVICE INSPECTION

3 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 Assessments

1. 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 Guidelines

1. 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. ISI-Site and vendor leads

b. Boric Acid Inspection

s and Evaluations

c. Reactor Vessel Head Inspection

-Site and vendor leads

d. SG Inspection

-Site and vendor leads

e. Aging Management Programs; and f. Site Welding Engineer

. B. On site 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.

DOCUMENT REQUEST FOR INSERVICE INSPECTION

4 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

DOCUMENT REQUEST FOR INSERVICE INSPECTION

5 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 1

0 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 SGs 1. 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 tubes

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

mechanism is identified

1. 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 tubes 1. 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, PD I-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.

DOCUMENT REQUEST FOR INSERVICE INSPECTION

6 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: S

G Examination Guidelines, SG

Integrity Assessment Guidelines, S G In-Situ Pressure Test Guidelines

1; and d. Boric Acid Corrosion Guidebook Revision 1

-Electric 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

.

1Note 1- If no SG examinations are planned for this outage, simply indicate

when the next SG examination will occur.