ML060200065

Notification of Inspection and Request for Information

ML060200065
Person / Time
Site:	North Anna
Issue date:	01/20/2006
From:	Lesser M Division of Reactor Safety II
To:	Christian D Virginia Electric & Power Co (VEPCO)
References
Download: ML060200065 (8)

Text

January 20, 2006 Virginia Electric and Power Company ATTN: Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060

SUBJECT:

NORTH ANNA POWER STATION, UNIT 1 - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION

Dear Mr. Christian:

On or about March 20-31, 2006, the NRC will perform the baseline inservice inspection (NRC Procedure 71111.08) at the North Anna Power Station, Unit 1.

In order to minimize the impact to your on-site 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 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 these inspection activities with your staff and understand that our regulatory contact for this inspection will be Jay Leberstein, of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector Kim Van Doorn at (404) 562-4643 (pkv@nrc.gov).

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).

Sincerely,

/RA/

Mark S. Lesser, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-338 License No. NPF-4

Enclosure:

(See next page)

VEPCO 2

Enclosure:

INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl:

Chris L. Funderburk, Director Nuclear Licensing and Operations Support Virginia Electric and Power Company Electronic Mail Distribution Jack M. Davis Site Vice President North Anna Power Station Electronic Mail Distribution Executive Vice President Old Dominion Electric Cooperative Electronic Mail Distribution County Administrator Louisa County P. O. Box 160 Louisa, VA 23093 Lillian M. Cuoco, Esq.

Senior Counsel Dominion Resources Services, Inc.

Electronic Mail Distribution Attorney General Supreme Court Building 900 East Main Street Richmond, VA 23219

OFFICE RII:DRS RII:DRS RII:DRP SIGNATURE /RA/ /RA/ /RA/

NAME PVanDoorn:pmd MLesser KLandis DATE 1/19/06 1/19/06 1/19/06 1/ /2006 1/ /2006 1/ /2006 1/ /2006 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: March 20-31, 2006 Inspection Procedures: IP 7111108 Inservice Inspection Activities Inspectors: Kim Van Doorn, (404) 562-4643 (pkv@nrc.gov)

Alex Vargas, (404) 562-4657 (aav@nrc.gov)

A. Information Requested for the In-Office Preparation Week The following information should be sent to the Region III office in hard copy (or electronic format CD - preferred), in care of K. Van Doorn by February 22, 2006, 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 on-site to your staff. We request that the specific items selected from the lists be available and ready for review on the first day of inspection. All information requests relate to Unit 1 unless otherwise stated. If you have any questions regarding this information, please contact the inspector as soon as possible.

1) A detailed schedule of:

a) Nondestructive examinations (NDE) planned for Class 1 & 2 systems and containment, performed as part of your ASME Code ISI Program during the scheduled inspection weeks.

b) Vessel head examinations which fulfill NRC commitments made in response to NRC Bulletin 2002-02, NRC Order EA-03-009 or are voluntary.

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

d) Inspections of Alloy 82/182/600 locations

2) A copy of the NDE procedures used to perform the examinations identified in A.1 (including calibration and flaw characterization/sizing procedures). 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 EPRI performance demonstration qualification summary sheets). Also, include documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers).

3) A copy of:

a) ASME Section XI, Code Relief Requests applicable to the examinations identified in A(1).

2 b) Correspondence with the NRC related to NRC Bulletin 2002-01 relative to the general boric acid inspection program and any additional response(s) to RAI requests regarding the boric acid inspection program.

4) A list identifying NDE reports (ultrasonic, radiography, magnetic particle, dye penetrant, visual (VT-1, VT-2, VT-3)) which have identified recordable indications on Code Class 1

& 2 systems since the beginning of the last refueling outage. Also, identify the NDE examinations with recorded indications in the vessel head penetration nozzles which have been accepted for continued service.

5) 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 or planned during the upcoming outage and identify the system, weld number and reference applicable documentation.

6) 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.

7) List with description of ISI and SG related issues (e.g. list based upon data base searches using key words related to piping or SG tube degradation such as cracks, wear, thinning, leakage, rust, corrosion, boric acid or errors in piping/SG tube examinations) entered into your corrective action system since the beginning of the last refueling outage (both Units).

8) 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.

9) Copy of SG history documentation given to vendors performing eddy current (ET) testing of the SGs during the upcoming outage.

10) 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.

11) Copy of previous outage SG tube operational assessment completed following ET of the SGs.

12) Copy of the document defining the planned ET scope for the SGs and the scope expansion criteria which will be used. Also, identify and describe any deviations in this scope or expansion criteria from the EPRI Guidelines.

13) Copy of the document describing the ET probe types, and ET acquisition equipment to be used, including which areas of the SG (e.g., top of tube sheet, U-bends) each probe will be used in. Also, provide your response letter(s) to Generic Letters 95-03, 95-05, 97-05, 97-06 and 04-01.

3

14) 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.

15) Identify what standards or requirements will be used to evaluate indications identified during NDE examinations of the reactor vessel head or pressurizer. (e.g. the specific industry or procedural standards which will be used to evaluate potential leakage indications. Including any plans to use chemical testing of leakage related deposits with applicable acceptance standards/criteria (e.g. 4 to 1 boron to lithium ratio, isotopic (CS 137/134 ratio) type analysis to date deposits).

16) If available electronically, please also provide a copy of your most current revision of the ISI Program Manual and Plan for this Interval. Can be provided during the first on site day if not available electronically.

17) List of any temporary non-code repairs in service.

18) List of known locations that have pin-hole leaks, ASME Class 1, 2, 3.

19) Please provide names and numbers for the following program leads:

ISI contacts (Examination, planning)

Containment Exams Snubbers and Supports Repair and Replacement program manager Site Welding Engineer Licensing contacts

20) 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.

21) Documentation of corrective action initiated and completed to address weaknesses in the boric acid inspection process resulting from the NRC Finding identified during the last Unit 2 outage involving a failure to identify locations of boric acid leakage.

B. Information to be provided on-site to the inspector (March 20, 2006):

1) For welds selected by the inspector from A.5 above (this selection will be provided by the inspector after review of the list), 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; c) Applicable Code Edition and Addenda for weldment; d) Applicable Code Edition and Addenda for welding procedures; e) Applicable weld procedures (WPS) used to fabricate the welds; f) Copies of procedure qualification records (PQRs) supporting the WPS on selected welds;

4 g) Copies of mechanical test reports identified in the PQRs above; h) Copies of the nonconformance reports for the selected welds; i) Radiographs of the selected welds and access to equipment to allow viewing radiographs; and j) Copies of the preservice examination records for the selected welds.

2) For the ISI related corrective action issues selected by the inspector from A.7 above, which will be provided by the inspector later, provide a copy of the corrective actions and supporting documentation.

3) For the nondestructive examination reports with relevant indications on Code Class 1 &

2 systems selected by the inspector from A.4 above and provided later, provide a copy of the examination records and associated corrective action documents.

4) Provide access to NDE personnel qualification and certification records. Also provide access to the qualification and certification procedure(s) used to qualify these personnel.

5) Updated schedules for item A.1 (including schedule showing contingency repair plans if available).

6) Provide access to information regarding possible repair processes (including drawings) for use on the vessel head nozzles and identify the repair procedures to be used. Also include access to any documented NRC reviews/evaluation/approval of these repair processes.

7) Provide a copy of the EPRI Technique Specification Sheets which support qualification of the ET probes to be used during the upcoming SG tube inspections.

8) Provide a copy of the guidance to be followed if a loose part or foreign material is identified in the SGs.

9) Copy of document describing actions to be taken if a new SG tube degradation mechanism is identified.

10) 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 tubes.

11) Ready access to the Editions of the ASME Code (Sections V, IX and XI) applicable to the inservice inspection program and the repair/replacement program. Ready access to the EPRI and industry standards referenced in the procedures used to perform the SG tube eddy current examination. (e.g. copies provided to the inspector to use for the duration of the inspection at the on-site inspection location).

5 Inspector Contact Information:

K. Van Doorn, Senior Reactor Inspector (404) 562-4643, pkv@nrc.gov Mailing Address US NRC Region 2 Attn: Kim Van Doorn 61 Forsyth Street, SW Atlanta, GA 30303 Suite 24T144