ML051180374

Re Notification of NRC Inservice Inspection and Request for Information

ML051180374
Person / Time
Site:	Point Beach
Issue date:	04/28/2005
From:	Dave Hills NRC/RGN-III/DRS/EEB
To:	Koehl D Nuclear Management Co
References
Download: ML051180374 (7)

Text

April 28, 2005 Mr. Dennis L. Koehl Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6590 Nuclear Road Two Rivers, WI 54241-9516

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNIT 1 - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION

Dear Mr. Koehl:

On October 11, 2005, the NRC will begin the baseline inservice inspection (NRC Procedure 71111.08) at the Point Beach Nuclear Plant, Unit 1. This on-site inspection is scheduled to be performed beginning the week of October 11, 2005, and is scheduled to conclude on November 18, 2005.

It is expected that this inspection will be 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. 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 inspection. The first set of documents is needed to support inspection preparation and we request that these be sent to the Region III office by September 23, 2005. The next set of documents are needed by the inspector upon arrival at the site on October 11, 2005.

We have discussed the detailed schedule for these inspection activities with Ms. F. Flentje of your staff and understand that our regulatory contact for this inspection will be Ms. F. Flentje of your organization. If there are any questions about this inspection or the material requested, please contact the inspector, Mr. Mel 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

D. Koehl 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/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-266 License Nos. DPR-24

Enclosure:

INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: F. Kuester, President and Chief Executive Officer, We Generation J. Cowan, Executive Vice President Chief Nuclear Officer D. Cooper, Senior Vice President, Group Operations J. McCarthy, Site Director of Operations D. Weaver, Nuclear Asset Manager Plant Manager Regulatory Affairs Manager Training Manager Site Assessment Manager Site Engineering Director Emergency Planning Manager J. Rogoff, Vice President, Counsel & Secretary K. Duveneck, Town Chairman Town of Two Creeks Chairperson Public Service Commission of Wisconsin J. Kitsembel, Electric Division Public Service Commission of Wisconsin State Liaison Officer

D. Koehl 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/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-306 License Nos. DPR-60

Enclosure:

INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: F. Kuester, President and Chief Executive Officer, We Generation J. Cowan, Executive Vice President Chief Nuclear Officer D. Cooper, Senior Vice President, Group Operations J. McCarthy, Site Director of Operations D. Weaver, Nuclear Asset Manager Plant Manager Regulatory Affairs Manager Training Manager Site Assessment Manager Site Engineering Director Emergency Planning Manager J. Rogoff, Vice President, Counsel & Secretary K. Duveneck, Town Chairman Town of Two Creeks Chairperson Public Service Commission of Wisconsin J. Kitsembel, Electric Division Public Service Commission of Wisconsin State Liaison Officer ADAMS Distribution:

WDR HKC RidsNrrDipmIipb GEG KGO DRPIII DRSIII PLB1 JRK1 DOCUMENT NAME: E:\Filenet\ML051180374.wpd To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RIII C RIII N RIII NAME DHills for PLouden DHills MHolmberg:tr DATE 04/28/05 04/28/05 04/28/05 OFFICIAL RECORD COPY

INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: October 11, 2005 - November 18, 2005 Inspection Procedures: IP 7111108, Inservice Inspection Inspector: Mel Holmberg (630) 829-9748 A. Information Requested for the In-Office Preparation Week The following information (electronic copy if practicable (e.g., CD ROM)) is requested by September 23, 2005, 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. All information requests relate to Unit 1 unless otherwise stated. If you have any questions regarding this information, please call the inspector as soon as possible.

1) A detailed schedule of:

(a) nondestructive examinations (NDE) planned for Class 1 and 2 systems and containment, performed as part of your ASME Code ISI Program during the scheduled inspection weeks; and (b) steam generator (SG) tube inspection and repair activities for the upcoming outage.

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

4) 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.

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 1 Enclosure

refueling 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., 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.

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.

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.

B. Information to be provided on-site to the inspector at the entrance meeting (October 11, 2005):

1) For welds selected by the inspector from A.5 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; 2 Enclosure

(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 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, 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.4 above, provide a copy of the examination records and associated corrective action documents.

4) Updated schedules for item A.1

5) Copy of the previous completed ASME Code leakage test for the reactor coolant system, documenting the results of the VT-2 inspections.

6) Copy of 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 EPRI Technique Specification Sheets which support qualification of the ET probes to be used during the upcoming SG tube inspections.

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

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

3 Enclosure

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 tubes.

12) 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).

4 Enclosure