ML110250760

Ltr. 01/25/11 Braidwood Unit 2 - Notification of NRC Inspection and Request for Information

ML110250760
Person / Time
Site:	Braidwood
Issue date:	01/25/2011
From:	Dave Hills NRC/RGN-III/DRS/EB1
To:	Pacilio M Exelon Generation Co, Exelon Nuclear
References
Download: ML110250760 (8)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 January 25, 2011

Mr. Michael J. Pacilio Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BRAIDWOOD STATION, UNIT 2 - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION

Dear Mr. Pacilio:

On April 20, 2011, the NRC will begin the baseline inservice inspection (NRC Inspection Procedure PI 71111.08) at the Braidwood Station, Unit 2. This on-site inspection is scheduled to be performed April 20, 2011 through May 6, 2011. 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 J. Gerrity, 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. 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.

M. Pacilio 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). Sincerely, /RA/ David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-457 License No. NPF-77

Enclosure:

INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: Distribution via ListServ INSERVICE INSPECTION DOCUMENT REQUEST 1 Enclosure Onsite Inspection Dates: April 20, 2011 - May 6, 2011 Inspection Procedures: IP 71111.08, Inservice Inspection (ISI) Inspectors: Mel Holmberg, Senior Reactor Engineer (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 March 31, 2011, 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. 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 (RI)-ISI Program, or other augmented inspection programs commitments as part of 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 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. 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).

INSERVICE INSPECTION DOCUMENT REQUEST 2 Enclosure

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 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. 14. Copy of the document describing the ET probe types, Examination Technique Specification Sheets, and ET acquisition equipment to be used.

INSERVICE INSPECTION DOCUMENT REQUEST 3 Enclosure

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 the First Day of the Inspection Following the Entrance Meeting. 1. For welds selected by the inspector from 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; 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); h. Copies of mechanical test reports identified in the PQRs above; i. Copies of the non-conformance 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 non-destructive 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.

INSERVICE INSPECTION DOCUMENT REQUEST 4 Enclosure

6. Copy 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. Fabrication Drawings (D size) of the: a. reactor vessel welds (if any are to be examined during the outage) and drawings provided to the NDE vendor to locate these welds. b. vessel head and penetration nozzles and J-groove welds (if any are to be examined during the outage) and drawings provided to the NDE vendor to locate these examination areas. 9. Provide a copy of the EPRI Examination Technique Specification Sheets, which support qualification of the ET probes to be used during the upcoming SG tube inspections. 10. Provide a copy of the guidance to be followed if a loose part or foreign material is identified in the SGs. 11. Copy of document describing actions to be taken if a new SG tube degradation mechanism is identified. 12. 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. 13. Provide documents with guidance/instructions for identifying and plugging SG tubes. 14. Copy of the document defining the planned scope for the reactor vessel head inspection (for visual, surface and volumetric exams). Also, identify extent of limitations in examination coverage if less than 90 percent of the examination volume can be achieved.

INSERVICE INSPECTION DOCUMENT REQUEST 5 Enclosure

15. For Unit 2, a copy of the current re-inspection year (RIY) calculation (Reference Code Case N-729-1, Section 2410 and Table 1, Item B.4.20) 16. 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 inservice inspection program and the repair/replacement program; b. 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 TR-107569, "Pressurized Water Reactor Steam Generator Examination Guidelines"; and c. Boric Acid Corrosion Guidebook Revision 1 - EPRI Technical Report 1000975. 17. Provide training (e.g., Scaffolding, Fall Protection, FME) if required to access the non-destructive or one time examinations scheduled for this outage. If you have questions regarding the information requested, please contact the lead inspector.

M. Pacilio 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). Sincerely, /RA/ David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-457 License No. NPF-77

Enclosure:

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

RidsNrrDorlLpl3-2 Resource Daniel Merzke RidsNrrPMBraidwood Resource RidsNrrDirsIrib Resource Cynthia Pederson Steven Orth Jared Heck Allan Barker DRPIII DRSIII Carole Ariano Linda Linn Patricia Buckley Tammy Tomczak ROPreports Resource DOCUMENT NAME: G:\DRSIII\DRS\Work in Progress\-Ltr 01__11 Brdwd 2 Request For Information MSH.docx 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 01/25/11 01/25/11 OFFICIAL RECORD COPY