ML073470930

Notification of Inspection and Request for Information

ML073470930
Person / Time
Site:	Davis Besse
Issue date:	12/13/2007
From:	Dave Hills NRC/RGN-III/DRS/EB1
To:	Bezilla M FirstEnergy Nuclear Operating Co
References
Download: ML073470930 (8)

Text

December 13, 2007 Mr. Mark B. Bezilla Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760

SUBJECT:

DAVIS BESSE NUCLEAR PLANT NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION

Dear Mr. Bezilla:

On January 2, 2008, the NRC will begin the Baseline Inservice Inspection (NRC Inspection Procedure PI 71111.08) at the Davis Besse Nuclear Power Station. This on-site inspection is scheduled to be performed January 2 through January 25, 2008.

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 on-site 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 on-site 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. B. Dotson, of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector Mr. J. Jandovitz at (630) 829-9763.

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

M. Bezilla Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-346;72-014 License No. NPF-3

Enclosure:

INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: The Honorable Dennis Kucinich J. Hagan, President and Chief Nuclear Officer - FENOC J. Lash, Senior Vice President of Operations and Chief Operating Officer - FENOC Richard Anderson, Vice President, Nuclear Support - FENOC Manager - Site Regulatory Compliance - FENOC D. Pace, Senior Vice President of Fleet Engineering - FENOC J. Rinckel, Vice President, Fleet Oversight - FENOC D. Jenkins, Attorney, FirstEnergy Corp.

Director, Fleet Regulatory Affairs - FENOC Manager - Fleet Licensing - FENOC Ohio State Liaison Officer R. Owen, Administrator, Ohio Department of Health Public Utilities Commission of Ohio President, Lucas County Board of Commissioners President, Ottawa County Board of Commissioners

M. Bezilla Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-346;72-014 License No. NPF-3

Enclosure:

INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: The Honorable Dennis Kucinich J. Hagan, President and Chief Nuclear Officer - FENOC J. Lash, Senior Vice President of Operations and Chief Operating Officer - FENOC Richard Anderson, Vice President, Nuclear Support - FENOC Manager - Site Regulatory Compliance - FENOC D. Pace, Senior Vice President of Fleet Engineering - FENOC J. Rinckel, Vice President, Fleet Oversight - FENOC D. Jenkins, Attorney, FirstEnergy Corp.

Director, Fleet Regulatory Affairs - FENOC Manager - Fleet Licensing - FENOC Ohio State Liaison Officer R. Owen, Administrator, Ohio Department of Health Public Utilities Commission of Ohio President, Lucas County Board of Commissioners President, Ottawa County Board of Commissioners DOCUMENT NAME:G:\DRS\Work in Progress\Ltr. 12__07 Davis Besse Request for Informtion JSJ.doc G Publicly Available G Non-Publicly Available G Sensitive G Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII C RIII N RIII N RIII NAME DEHills forJJandovitz: ls KReimer DHills DATE 12/13/07 12/13/07 12/13/07 OFFICIAL RECORD COPY

Letter to Mr. M. Bezilla from Mr. D. E. Hills dated December 13, 2007.

SUBJECT:

DAVIS BESSE NUCLEAR POWER STATION NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION DISTRIBUTION:

RAG1 TEB SPS1 TJW2 RidsNrrDirsIrib MAS KGO JKH3 JER7 CAA1 DRPIII DRSIII PLB1 TXN ROPreports@nrc.gov

INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: January 2 through January 25, 2008 Inspection Procedures: IP 71111.08, Inservice Inspection Inspectors: John Jandovitz (630) 829-9763 Jsj1@nrc.gov A. Information Requested for the In-Office Preparation Week The following information (electronic copy CD ROM if possible) is requested by December 28, 2007, 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 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. If you have any questions regarding this information, please call the inspector as soon as possible.

1) 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 ISI Program, and NDE examinations planned for other systems performed as part of a Risk Informed (RI)-ISI Program, or other programs committed to as part of an industry initiative such as Alloy 600 inspections and MRP -139 during the scheduled inspection weeks, to include:

• System Identification

• Component Identification

• Class

• Examination Category

• Examination Item Number

• Weld Number

• Exam Type (VT, UT, MT, etc.)

• NDE Procedure Number for Each Exam

• Date and Time of Exam

• Code Edition and Addenda Committed to

b. steam generator (SG) tube inspection and repair activities for the upcoming outage; and 1 Enclosure

c. any training required to observe these examinations; e.g., confined space, scaffolding, fall protection.

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 including serial numbers).

3) A copy of ASME Section XI, Code Relief Requests applicable to the examinations identified in 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, dye penetrant, visual (VT-1, VT-2, VT-3), which have identified relevant indications on Code Class 1 and 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.

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.

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 (e.g., piping/SG tube degradation or damage or errors in piping/SG tube examinations) entered into your corrective action system 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 outage.

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 testing.

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

13) 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.

2 Enclosure

14) Copy of the document describing the ET probe types, ETTS documents, and ET acquisition equipment to be used, including which areas of the SG (e.g., top of tube sheet, ) 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.

15) 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.

B. Information to be provided on-site to the inspector following the entrance meeting (January 2, 2008).

1) For welds selected by the inspector from 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;

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;

g. Copies of welders performance qualification records (WPQ);

h. Copies of mechanical test reports identified in the PQRs above;

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

j. Radiographs of the selected welds and access to equipment to allow viewing radiographs; and

k. Copies of the preservice examination records for the selected welds.

2) For the ISI related corrective action issues selected by the inspector from A.8 above, provide a copy of the corrective actions and supporting documentation.

3) For the nondestructive examination reports with relevant indications on Code Class 1 and 2 systems selected by the inspector from 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) Copy of documentation including nondestructive examination reports for the last upper vessel head examination.

6) Copy of evaluation or calculation demonstrating the scope of the visual examination of the upper head will meet the 95 percent minimum coverage required by NRC Order EA-03-009 (if a visual examination is planned).

7) Provide the susceptibility ranking calculation for the vessel head operating time and temperature. Also, provide the plant specific records (or vendor information) used to determine the inputs for this calculation.

3 Enclosure

8) 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.

9) Copy of any documentation of:

a. engineering evaluations/assessments of boric acid related deposits and associated wastage or corrosion for safety significant components; and

b. corrective actions for coolant leakage including boric acid deposits on safety related components identified since the beginning of the last refueling outage.

10) 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.

11) 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.

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

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

14) 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.

15) 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 which includes EPRI documents: TR-107621-R1, Steam Generator Integrity Assessment Guidelines, Revision 1; TR-107620-R1, Steam Generator In-Situ Pressure Test Guidelines, Revision 1; and 1003138, Pressurized Water Reactor Steam Generator Examination Guidelines: Revision 6. (or latest revision)

These copies are provided to the inspector to use for the duration of the inspection at the on-site inspection location and will be returned at the end of the inspection.

4 Enclosure