ML093640786

Ltr. 12/30/09 D. C. Cook Notification of Inspection and Request for Information

ML093640786
Person / Time
Site:	Cook
Issue date:	12/30/2009
From:	Dave Hills NRC/RGN-III/DRS/EB1
To:	Jensen J Indiana Michigan Power Co
References
Download: ML093640786 (8)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 December 30, 2009 Mr. Joseph Jensen Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106

SUBJECT:

D.C. COOK NUCLEAR POWER PLANT UNIT 1 - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION

Dear Mr. Jensen:

On March 8, 2010, the NRC will begin the baseline inservice inspection (Inspection Procedure 71111.08) and a review of the Reactor Coolant System Dissimilar Metal Welds (Temporary Instruction 2515/172) at the D.C. Cook Nuclear Power Plant Unit 1. This on-site inspection is scheduled to be performed March 8, 2008 through March 26, 2010.

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 Mr. R. West, of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector Mr. M. Holmberg at (630) 829-9748.

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), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

J. Jenson 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.

Sincerely,

/RA/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-315 License No. DPR-58

Enclosure:

INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: Distribution via ListServ

INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: March 8-26, 2010 Inspection Procedures: IP 71111.08, Inservice Inspection Inspector: Mel Holmberg (630) 829-9748 mel.holmberg@nrc.gov A. Information Requested for the In-Office Preparation Week The following information (electronic copy CD ROM if possible) is requested by February 22, 2010, 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 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 (RI)-ISI Program, or other augmented inspection programs commitments as part of an industry initiative. Specifically, identify any dissimilar metal weld examinations performed to meet the MRP-139 Program that are scheduled to occur during the outage. 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 exam;

b. reactor vessel upper head examinations required by 10 CFR 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; and

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

Also, provide the inspector with the on-site training necessary to observe these activities; (e.g., confined space, scaffolding, or fall protection).

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INSERVICE INSPECTION DOCUMENT REQUEST

2. A copy of the NDE procedures and welding procedures used to perform the activities identified in 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 EPRI performance demonstration qualification summary sheets).

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, 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 (e.g., piping/SG tube degradation or damage (cracks, wall thinning, wear, MIC) or errors identified in piping/SG tube examinations) entered into your corrective action system since the beginning of the last refueling outage (both Units). Also, include a list of corrective action records associated with foreign material introduced/identified in the primary or secondary piping systems since the beginning of the last refueling outage (both Units).

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 typically given to vendors performing eddy current (ET) testing of the Steam Generators (SGs).

11. Copy of the latest Unit 1 SG tube condition monitoring assessment.

12. Copy of the current Unit 1 SG tube operational assessment. Also, identify any changes made to this document since document was originally issued and the basis for those changes.

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INSERVICE INSPECTION DOCUMENT REQUEST

13. Copy of the document defining the previous Unit 1 ET scope for the SGs and the previous outage tube inspection results identifying the list of degraded or defective tubes.

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 changes made to the dissimilar metal weld examination program (MRP) for Unit 2 welds subject to the requirements of the Materials Reliability Program:

Primary System Piping Butt Weld Inspection and Evaluation Guidelines (MRP-139), which have been implemented since the completion of the last NRC inspection (2008). For example, identify a program change if welds have been moved in/out of scope, schedules of planned weld examinations have been changed, or planned methods for mitigation of susceptible welds have changed since the NRC documented its review of this program in inspection report 05000315/2008003.

16. For any deviations from the Materials Reliability Program: Primary System Piping Butt Weld Inspection, and Evaluation Guidelines (MRP-139), provide a copy of the basis document supporting these deviations and correspondence with NEI, MRP and the NRC related to these deviations.

17. Identify and provide scheduled dates for any dissimilar metal weld mitigation activities (overlay repair, inlay repair, mechanical stress improvement, etc.),

which will occur during the upcoming refueling outage and identify the welds to be mitigated.

B. Information To Be Provided On-Site to the Inspector Following the Entrance Meeting.

1. For welds selected by the inspector from A.2 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;

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;

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

3 Enclosure

INSERVICE INSPECTION DOCUMENT REQUEST

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 pre-service 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 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.

6. 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.

7. 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.

8. Provide a copy of the site specific documents, which implement the MRP-139 Program, and a copy of the baseline and inservice inspection schedules for the welds affected by this program.

9. Identify any dissimilar welds, which were excluded from the MRP-139 Guidelines, where the site is relying on NSSS vendor documents to exclude these welds from this program. For these welds, (if any) provide a copy of the NSSS vendor documents and site documents, which provide the basis for excluding these welds from the MRP-139 Program.

10. If Mechanical Stress Improvement (MSI) is to be performed on MRP-139 Welds, provide:

4 Enclosure

INSERVICE INSPECTION DOCUMENT REQUEST

a. A copy of the stress analysis and design change documents supporting this activity.

b. Vendor procedures, equipment specifications and personnel qualifications for the MSI.

c. Weld fabrication drawings for the affected welds subject to MSI.

d. Piping support configuration drawings for supports nearest welds subject to MSI.

11. Fabrication Drawings (D size) of the reactor vessel welds to be examined and drawings provided to the NDE vendor to locate these welds.

12. Ready access to:

a. Sections V, IX, and XI of the ASME Code with Editions applicable to the inservice inspection program and the repair/replacement program;

b. MRP-139, Materials Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guideline and associated site implementing procedures; and

c. EPRI and industry standards referenced in the site procedures used to perform the SG tube eddy current examination, which includes EPRI documents: TR-107621-R1, Steam Generator Integrity Assessment Guidelines, TR-107620-R1, Steam Generator In-Situ Pressure Test Guidelines, and 1003138, Pressurized Water Reactor Steam Generator Examination Guidelines.

Ready access is typically facilitated by providing copies of these standards at the on-site NRC inspection location for the duration of the inspection.

5 Enclosure

J. Jenson 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.

Sincerely,

/RA/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-315 License No. DPR-58

Enclosure:

INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: Distribution via ListServ DISTRIBUTION:

Susan Bagley RidsNrrDorlLpl3-1 Resource RidsNrrPMDCCook Resource RidsNrrDirsIrib Resource Cynthia Pederson Steven Orth Jared Heck Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Patricia Buckley Tammy Tomczak ROPreports Resource DOCUMENT NAME: G:\DRS\WIP\Ltr 123009 DCCOOK Request for Information MSH.doc Publicly Available Non-Publicly Available Sensitive 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 RIII NAME MHolmberg:ls DHills DATE 12/30/09 12/30/09 OFFICIAL RECORD COPY