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Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2017004; 05000306/2017004 (Exf)
	ML17249A923
Person / Time
Site:	Prairie Island
Issue date:	09/06/2017
From:	Edison Fernandez; NRC/RGN-III/DRS/EB1
To:	Northard S; Northern States Power Co
References
	IR 2017004
	Download: ML17249A923 (8)
	v • d • e

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION III

2443 WARRENVILLE RD. SUITE 210

LISLE, IL 60532-4352

September 6, 2017

Mr. Scott D. Northard

Site Vice President

Prairie Island Nuclear Generating Plant

Northern States Power Company, Minnesota

1717 Wakonade Drive East

Welch, MN 55089-9642

SUBJECT: PRAIRIE ISLAND STATION, UNIT 2NOTIFICATION OF NRC BASELINE

INSPECTION AND REQUEST FOR INFORMATION; INSPECTION

REPORT 05000282/2017004; 05000306/2017004

Dear Mr. Northard:

On October 16, 2017, the U. S. Nuclear Regulatory Commission (NRC) will begin the Baseline

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

October 16, 2017, through October 26, 2017.

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 to ensure that the inspector is adequately

prepared. The second group identifies the information the inspector 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 inspection activities with your staff and understand that our

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

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

Mr. Edison Fernandez at 630 829-9754 or via e-mail at Edison.Fernandez@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.

S. Northard -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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Edison Fernandez

Engineering Branch 1

Division of Reactor Safety

Docket Nos. 50-282, 50-306

License Nos. DPR-42, DPR-60

Enclosure:

Inservice Inspection Document Request

cc: Distribution via LISTSERV

S. Northard -3-

Letter to Scott Northard from Edison Fernandez dated September 6, 2017

SUBJECT: PRAIRIE ISLAND STATION, UNIT 2NOTIFICATION OF NRC BASELINE

INSPECTION AND REQUEST FOR INFORMATION; INSPECTION

REPORT 05000282/2017004; 05000306/2017004

DISTRIBUTION:

Jeremy Bowen

RidsNrrPMPrairieIsland Resource

RidsNrrDorlLpl3

RidsNrrDirsIrib Resource

Cynthia Pederson

DRPIII

DRSIII

ADAMS Accession Number ML17249A923

OFFICE RIII RIII RIII RIII

NAME EFernandez:cl

DATE 09/06/17

OFFICIAL RECORD COPY

INSERVICE INSPECTION DOCUMENT REQUEST

Inspection Dates: October, 16, 2017, through October, 26, 2017

Inspection Procedures: IP 71111-08, Inservice Inspection

Lead Inspector: Edison Fernandez, DRS

630-829-9754

Edison.Fernandez@nrc.gov

A. Information for the In-Office Preparation Week

The following information is requested as an (electronic copy CD ROM if possible) by

October 9, 2017, to facilitate the selection of specific items that will be reviewed during

the on-site inspection week. The inspector will select specific items from the information

requested below and a list of additional documents needed on-site from your staff. We

request that the specific items selected from the lists be available and ready for review

on the first day of inspection. The following information is applicable to Unit 2 unless

otherwise indicated. If you have any questions regarding this information, please call the

inspector as soon as possible.

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

a. non-destructive examinations (NDE) planned for Class 1 and 2 Systems and

containment, performed as part of your ASME Code Inservice Inspection (ISI)

Program (include edition and addenda of Code committed to), and NDE

examinations planned for other systems performed as part of a Risk-Informed

ISI Program, or other augmented inspection programs (e.g., ASME Code

Case N-770-1 examination of dissimilar metal welds and examinations to

meet an industry initiative). 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;

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-729-1;

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

outage or SG secondary side examinations1; and

d. welding on Code Class 1, 2, or 3 components.

2. A copy of the NDE procedures and welding procedures used to perform

the activities identified in Item A.1 (including NDE calibration and flaw

characterization/sizing procedures and Welding Procedure Qualification

Records). For ultrasonic examination procedures qualified in accordance

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

supporting the procedure qualification (e.g., the Electric Power Research

Institute (EPRI) performance demonstration qualification summary sheets).

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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

3. A copy of ASME Section XI, Code Relief Requests applicable to the

examinations identified in Item A.1. This would include the U.S. Nuclear

Regulatory Commission (NRC) approved Relief Request for implementing a

risk-informed ISI Program (if applicable).

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. 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 and identify the system, weld number, and

reference applicable documentation (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. List with description of ISI and SG-related issues such as piping or SG tube

degradation or damage (e.g., cracks, wall thinning, wear, microbiologically

induced corrosion) or errors identified during piping/SG tube examinations that

have been entered into your corrective action system since the beginning of the

last refueling outage. Also, include a list of corrective action records associated

with foreign material introduced/identified in the reactor vessel, primary coolant

system, SG or feed systems since the beginning of the last refueling outage.

9. 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.

10. Copy of SG history documentation given to vendors performing eddy current (ET)

testing of the SGs during the upcoming outage1.

11. 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. Copy of previous outage SG tube operational assessment completed following

ET of the SGs1.

13. 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 EPRI Guidelines1.

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.

2

14. 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).

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

locating the tubes that require repair) and plugging SG tubes1.

16. 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.

17. Copy of current calculations for EDY, and RIY as defined in Code Case N-729-1

that establish the volumetric and visual examination frequency for the reactor

vessel head and J-groove welds.

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

a. Inservice Inspection-Site and vendor leads

b. Boric Acid Inspections and Evaluations

c. Reactor Vessel Head Inspection-Site and vendor leads

d. SG Inspection-Site and vendor leads

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);

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 procedures and weld data sheets used to fabricate the

welds;

f. Copies of procedure qualification records supporting the weld procedures;

g. Copies of welders performance qualification records;

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.

3

h. Copies of mechanical test reports identified in the 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; and

k. Copies of the pre-service examination records 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. Updated schedules for

Item A.1 (including schedule showing contingency repair plans if available).

4. 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.

5. Copy of:

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

associated wastage or corrosion for safety significant components; and

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

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

outage.

6. 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.

7. 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.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).

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

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

9. Provide a copy of the EPRI Examination Technique Specification Sheets and

vendor documents, which support qualification of the ET probes to be used

during the upcoming SG tube inspections1.

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.

4

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

identified in the SGs1.

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

defective SG tubes (including any NRC reviews/evaluation/approval of this repair

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

identified in the SG tubes1.

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

mechanism is identified1.

13. 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).

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

locating the tubes that require repair) and plugging SG tubes1.

15. Provide copies of the following standards at the on-site NRC 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.);

c. EPRI and industry standards referenced in the site procedures used to

perform the SG tube ET examination, which includes EPRI documents:

TR-107621-R1, Steam Generator Integrity Assessment Guidelines,

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

SG Management Program: SG Integrity Assessment Guidelines, Part 10,

and 1003138, Pressurized Water Reactor Steam Generator Examination

Guidelines1; and

d. Boric Acid Corrosion Guidebook Revision 2-EPRI Technical Report 1000975.

16. Provide training (e.g., Scaffolding, Fall Protection, FME) 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.

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ML17249A923

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