ML092720921

Notification of Inspection (NRC Inspection Report 05000382/2009005) and Request for Information

ML092720921
Person / Time
Site:	Waterford
Issue date:	09/29/2009
From:	Ray Kellar Region 4 Engineering Branch 1
To:	Kowalewski J Entergy Operations
References
IR-09-005
Download: ML092720921 (12)

See also: IR 05000382/2009005

Text

UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV612 EAST LAMAR BLVD, SUITE 400ARLINGTON, TEXAS 76011-4125September 29, 2009

Joseph Kowalewski, Vice President, Operations Entergy Operations, Inc. Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093

SUBJECT: WATERFORD STEAM ELECTRIC STATION, UNIT 3 - NOTIFICATION OF INSPECTION (NRC INSPECTION REPORT 05000382/2009005) AND REQUEST FOR INFORMATION

Dear Mr. Kowalewski:

From November 2-13, 2009, reactor inspectors from the U. S. Nuclear Regulatory Commission's (NRC) Region IV office will perform the baseline inservice inspection at the Waterford Steam Electric Station, Unit 3, using NRC Inspection Procedure 71111.08, "Inservice Inspection Activities," and Temporary Instruction 2515/172, "Reactor Coolant System Dissimilar Metal Butt Welds." Experience has shown that this inspection is a resource intensive inspection both for the NRC inspectors and your staff. In order to minimize the impact to your onsite 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 (Section A of the enclosure) identified information to be provided prior to the inspection to

ensure that the inspectors are adequately prepared. The second group (Section B of the enclosure) identifies the information the inspectors 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 and information required for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Mr. Jim Pollock of your licensing organization. Our inspection dates are subject to change based on your updated schedule of outage activities. If there are any questions about this inspection or the material requested, please contact the lead inspector Ramon Azua at (817) 319-4376

(ray.azua@nrc.gov) or Michael Bloodgood at (817) 276-6544 (michael.bloodgood@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).

Entergy Operations, Inc. - 2 -

Sincerely, /RA/

Ray Kellar, P.E., Chief Engineering Branch 1 Division of Reactor Safety

Docket: 50-382 License: NPF-38

Enclosure: Inservice Inspection Document Request

Senior Vice President

Entergy Nuclear Operations P. O. Box 31995 Jackson, MS 39286-1995

Senior Vice President and

Chief Operating Officer Entergy Operations, Inc. P. O. Box 31995 Jackson, MS 39286-1995

Vice President, Operations Support Entergy Services, Inc. P. O. Box 31995 Jackson, MS 39286-1995

Senior Manager, Nuclear Safety and Licensing Entergy Services, Inc. P. O. Box 31995 Jackson, MS 39286-1995

Site Vice President Waterford Steam Electric Station, Unit 3 Entergy Operations, Inc. 17265 River Road Killona, LA 70057-0751

Director Nuclear Safety Assurance Entergy Operations, Inc. 17265 River Road Killona, LA 70057-0751

Entergy Operations, Inc. - 3 -

General Manager, Plant Operations Waterford 3 SES Entergy Operations, Inc. 17265 River Road

Killona, LA 70057-0751

Manager, Licensing Entergy Operations, Inc. 17265 River Road

Killona, LA 70057-3093

Chairman Louisiana Public Service Commission P. O. Box 91154 Baton Rouge, LA 70821-9154

Parish President Council St. Charles Parish P. O. Box 302 Hahnville, LA 70057

Director, Nuclear Safety & Licensing Entergy, Operations, Inc. 440 Hamilton Avenue White Plains, NY 10601

Louisiana Department of Environmental Quality, Radiological Emergency Planning and Response Division P. O. Box 4312 Baton Rouge, LA 70821-4312

Chief, Technological Hazards Branch FEMA Region VI 800 North Loop 288

Federal Regional Center Denton, TX 76209

Entergy Operations, Inc. - 4 -

Electronic distribution by RIV: Regional Administrator (Elmo.Collins@nrc.gov) Deputy Regional Administrator (Chuck.Casto@nrc.gov)

DRP Director (Dwight.Chamberlain@nrc.gov) DRP Deputy Director (Anton.Vegel@nrc.gov) DRS Director (Roy.Caniano@nrc.gov) DRS Deputy Director (Troy.Pruett@nrc.gov) Senior Resident Inspector (Mark.Haire@nrc.gov)

Resident Inspector (Dean.Overland@nrc.gov) Branch Chief, DRP/E (Jeff.Clark@nrc.gov) Senior Project Engineer, DRP/E (Ray.Azua@nrc.gov) WAT Site Secretary (Linda.Dufrene@nrc.gov) Public Affairs Officer (Victor.Dricks@nrc.gov) Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov) RITS Coordinator (Marisa.Herrera@nrc.gov)

Regional Counsel (Karla.Fuller@nrc.gov) Congressional Affairs Officer (Jenny.Weil@nrc.gov) OEMail Resource

Inspection Reports/MidCycle and EOC Letters to the following:

ROPreports DRS STA (Dale.Powers@nrc.gov) OEDO RIV Coordinator (Leigh.Trocine@nrc.gov)

SUNSI Review Completed: ___Y___ ADAMS: Yes No Initials: _RVA

Publicly Available Non-Publicly Available Sensitive Non-Sensitive R:\REACTORS\W3 ISI RFI - RVA ML09270921

SPE:DRP/PBE RI:DRS/EB1 C:DRS/EB1

RVAzua MRBloodgood RLKellar /RA/ /RA//RA/ 09/29/09 09/29/09 09/29/09 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax

- 1 - Enclosure INSERVICE INSPECTION DOCUMENT REQUEST

Inspection Dates: November 2-13, 2009

Inspection Procedures: IP 71111.08 "Inservice Inspection (ISI) Activities" TI 2515/172 "Reactor Coolant System Dissimilar Metal Butt Welds" Inspectors: Ramon Azua, Senior Project Engineer (Lead Inspector - ISI) Michael Bloodgood, Reactor Inspector

A. Information Requested for the In-Office Preparation Week

The following information should be sent to the Region IV office in hard copy or electronic format (ims.certrec.com preferred), in care of Ramon Azua, by October 26, 2009, 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 then request from your staff additional documents needed during the onsite inspection week (Section B of this enclosure). We ask that the specific items selected from the lists be available and ready for review on the first day of inspection. *Please provide requested documentation electronically if possible. If requested documents are large and only hard copy formats are available, please inform the inspector(s), and provide subject documentation during the first day of the onsite inspection. If you have any questions regarding this information request, please call the inspector as soon as possible.

A.1 ISI/Welding Programs and Schedule Information

a) A detailed schedule (including preliminary dates) of:

i) Nondestructive examinations (NDEs) planned for Class 1 & 2 systems and containment, performed as part of your ASME Section XI, Risk

Informed (if applicable), and augmented ISI programs during the upcoming outage.

Provide a status summary of the NDE inspection activities vs. the required inspection period percentages for this Interval by category per

ASME Section XI, IWX-2400 (Do not provide separately if other documentation requested contains this information)

ii) Reactor pressure vessel head (RPVH) examinations planned for the upcoming outage.

iii) Examinations planned for Alloy 82/182/600 components that are not included in the Section XI scope. (If applicable)

iv) Examinations planned as part of your Boric Acid Corrosion Control Program (Mode 3 walkdowns, bolted connection walkdowns, etc.)

- 2 - Enclosure

v) Welding activities that are scheduled to be completed during the upcoming outage (ASME Class 1, 2, or 3 structures, systems, or components (SSCs)).

b) A copy of ASME Section XI Code Relief Requests and associated NRC Safety Evaluations applicable to the examinations identified above.

c) A list of NDE reports (ultrasonic, radiography, magnetic particle, dye penetrate, Visual VT-1, VT-2, and VT-3), which have identified relevant conditions on Code Class 1 & 2 systems since the beginning of the last refueling outage. This should include the previousSection XI pressure test(s) conducted during start up and any evaluations associated with the results of the pressure tests. Also, include in the list the NDE reports with relevant conditions in the RPVH penetration nozzles which have been accepted for continued service. The list of NDE reports should include a brief description of the SSC where the relevant condition was identified.

d) A list with a brief description (e.g., system, material, pipe size, weld number, and NDE performed) 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 are planned to be fabricated this refueling outage.

e) If reactor vessel weld examinations required by the ASME Code are scheduled to occur during the upcoming outage, provide a detailed description of the welds to be examined and the extent of the planned examination. Please also provide reference numbers for applicable procedures that will be used to conduct these examinations.

f) Copy of any 10 CFR Part 21 reports applicable to your SSCs within the scope of Section XI of the ASME Code that have been identified since the beginning of the last refueling outage.

g) A list of any temporary non-code repairs in service (e.g., pinhole leaks).

h) Please provide copies of the most recent self assessments for the ISI, Welding, and Alloy 600 Programs.

A.2 Reactor Pressure Vessel Head (RPVH)

a) Provide the detailed scope of the planned NDE of the reactor vessel head which identifies the types of NDE methods to be used on each specific part of the vessel head to fulfill commitments made in response to NRC Bulletin 2002-02 and NRC Order EA-03-009 or ASME Code Case N-729-1. Also, include examination scope expansion criteria and planned expansion sample sizes if

relevant conditions are identified. (If applicable)

b) A list of the standards and/or requirements that will be used to evaluate indications identified during NDE of the reactor vessel head (e.g., the specific

- 3 - Enclosure industry or procedural standards which will be used to evaluate potential leakage and/or flaw indications).

A.3 Boric Acid Corrosion Control Program (BACCP)

a) Copy of the procedures that govern the scope, equipment and implementation of the inspections required to identify boric acid leakage and the procedures for boric acid leakage/corrosion evaluation.

b) Please provide a list of leaks (including Code class of the components) that have been identified since the last refueling outage and associated corrective action documentation. If during the last cycle, the Unit was shutdown, please provide documentation of containment walkdown inspections performed as part of the BACCP. c) Please provide a copy of the most recent self-assessment performed for the BACCP. A.4 Steam Generator Tube (SGT) Inspections

a) A detailed schedule of:

i) SGT inspection, data analyses, and repair activities for the upcoming outage. (If occurring)

ii) SG secondary side inspection activities for the upcoming outage. (If occurring)

b) Please provide a copy of your SG ISI Inspection Program and Plan. Please include a copy of the Operational Assessment from last outage and a copy of the following documents as they become available:

i) Degradation Assessment ii) Condition Monitoring Assessment

c) If you are planning on modifying your Technical Specifications such that they are consistent with TSTF-449, please provide copies of your correspondence with

the NRC regarding deviations from the STS.

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

e) Copy of SG Eddy Current Data Analyst Guidelines and Site Validated Eddy Current Technique Specification Sheets (ETSS). Additionally, please provide a copy of EPRI Appendix H ETSS Qualification Records.

- 4 - Enclosure f) Identify and quantify any SGT leakage experienced during the previous operating cycle. Also provide documentation identifying which SG was leaking and corrective actions completed or planned for this condition (If applicable).

g) Provide past history of the condition and issues pertaining to the secondary side of the steam generators (including items such as loose parts, fouling, top of tube sheet condition, crud removal amounts, etc.)

h) Please provide copies of your most recent self assessments of the SG monitoring, loose parts monitoring, and secondary side water chemistry control

programs.

i) Please also indicate where the primary, secondary, and resolution analyses are scheduled to take place.

j) Please provide a summary of the scope of the SGT examinations, including examination methods such as Bobbin, Rotating Pancake, or Plus Point, and the

percentage of tubes to be examined. *Do not provide these documents separately if already included in other information requested. A.5 Materials Reliability (MRP-139) Program Activities

a) A list of, with verification, that the baseline inspections of all applicable Dissimilar Metal Butt Welds (DMBWs) have been completed by September 30, 2009.

b) Verification that baseline inspection of hot leg and cold leg temperature DMBWs have been included in the inspection program and that the schedules for the

baseline inspections are consistent with the baseline schedules in MRP-139.

c) A list and schedule (examination dates) of all DMBW examinations planned for the upcoming refueling outage. If none are scheduled, then data from previous examinations should be available for review.

d) A list and schedule for any welding to be performed on DMBWs in the upcoming outage. If no welding will be performed then records of previous welding on DMBWs and postweld NDE documentation.

e) A list and schedule of any stress improvement (SI) activities planned for the upcoming refueling outage. If none are scheduled then have qualification reports for any SIs previously performed.

f) Documentation and description of how the baseline and inservice inspection specifications in MRP-139 are satisfied at your facility.

g) A list of weld locations controlled by MRP-139 which includes the MRP-139 weld category, pre-mitigation volumetric examination date, type of mitigation or stress improvement, post mitigation volumetric examination date, and plans for future MRP-139 required examinations.

- 5 - Enclosure

A.6 Additional information related to all ISI activities

a) A list with a brief description of ISI, BACCP, and SGT inspection related issues (e.g., condition reports) entered into your corrective action program since the

beginning of the last refueling outage. For example, a list based upon data base searches using key words related to piping or SG tube degradation such as: ISI, ASME Code,Section XI, NDE, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or errors in piping/SGT examinations.

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

ISI contacts (Examination, planning) Containment Exams RPVH Exams Snubbers and Supports Repair and Replacement Program Manager

Licensing Contact Site Welding Engineer Boric Acid Corrosion Control Program SG Inspection Activities (site lead and vendor contact)

B. Information to be provided onsite to the inspector(s) at the entrance meeting (November 2, 2009):

B.1 ISI / Welding Programs and Schedule Information

a) Updated schedules for ISI/NDE activities, including SGT inspections, planned welding activities, and schedule showing contingency repair plans, if available.

b) For ASME Code Class 1 and 2 welds selected by the inspector from the lists provided from section A of this enclosure, please provide copies of the following

documentation for each subject weld:

i) Weld data sheet (traveler) ii) Weld configuration and system location iii) Applicable Code Edition and Addenda for weldment

iv) Applicable Code Edition and Addenda for welding procedures v) Applicable weld procedures (WPS) used to fabricate the welds vi) Copies of procedure qualification records (PQRs) supporting the WPS from B.1.b.v vii) Copies of mechanical test reports identified in the PQRs above viii) Copies of the nonconformance reports for the selected welds (If applicable) ix) Radiographs of the selected welds and access to equipment to allow viewing radiographs (If RT was performed) x) Copies of the preservice examination records for the selected welds.

- 6 - Enclosure xi) Copies of welder performance qualifications records applicable to the selected welds, including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS (at least six months prior to the date of subject work) xii) Copies of NDE personnel qualifications (VT, PT, UT, RT), as applicable

c) For the ISI related corrective action issues selected by the inspector(s) from section A of this enclosure, provide a copy of the corrective actions and supporting documentation.

d) For the NDE reports with relevant conditions on Code Class 1 & 2 systems selected by the inspector from section A above, provide a copy of the examination records, examiner qualification records, and associated corrective action documents.

e) A copy of (or ready access to) most current revision of the ISI Program Manual and Plan for the current Interval.

f) For the NDEs selected by the inspector from section A of this enclosure, provide copy of the NDE procedures used to perform the examinations (including calibration and flaw characterization/sizing procedures). For ultrasonic examination procedures qualified in accordance with ASME Code,Section XI,

Appendix VIII, provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets). Also, include qualification documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers) and NDE personnel qualification records.

B.2 Reactor Pressure Vessel Head (RPVH)

a) Provide the NDE personnel qualification records for the examiners who will perform examinations of the RPVH.

b) Provide drawings showing the following: (If a visual examination is planned for the upcoming refueling outage)

i) RPVH and CRDM nozzle configurations

ii) RPVH insulation configuration

The drawings listed above should include fabrication drawings for the nozzle attachment welds as applicable.

c) Copy of NDE reports from the last RPVH examination.

d) Copy of evaluation or calculation demonstrating that the scope of the visual examination of the upper head will meet the 95 percent minimum coverage required by NRC Order EA-03-009 or ASME Code Case N-729-1 (If a visual examination is planned for the upcoming refueling outage).

- 7 - Enclosure

e) Provide a copy of the procedures that will be used to identify the source of any boric acid deposits identified on the RPVH. If no explicit procedures exist which govern this activity, provide a description of the process to be followed including personnel responsibilities and expectations.

f) Provide a copy of the updated calculation of effective degradation years (EDY) for the RPVH susceptibility ranking.

g) Provide copy of the vendor qualification report(s) that demonstrates the detection capability of the NDE equipment used for the RPVH examinations. Also, identify any changes in equipment configurations used for the RPVH examinations which differ from that used in the vendor qualification report(s).

B.3 Boric Acid Corrosion Control Program (BACCP)

a) Please provide boric acid walkdown inspection results, an updated list of boric acid leaks identified so far this outage, associated corrective action documentation, and overall status of planned boric acid inspections.

b) Please provide any engineering evaluations completed for boric acid leaks identified since the end of the last refueling outage. Please include a status of

corrective actions to repair and/or clean these boric acid leaks. Please identify specifically which known leaks, if any, have remained in service or will remain in service as active leaks.

B.4 Steam Generator Tube (SGT) Inspections

a) Copies of the Examination Technique Specification Sheets (ETSS) and associated justification for any revisions.

b) Copy of the guidance to be followed if a loose part or foreign material is identified in the SGs.

c) Please provide a copy of the ET procedures used to perform the SGT inspections (specifically calibration and flaw characterization/sizing procedures, etc.). Also include documentation for the specific equipment to be used.

d) Please provide copies of your responses to NRC and industry operating experience communications such as Generic Letters, Information Notices, etc. (as applicable to SGT inspections) *Do not provide these documents separately if already included in other information requested such as the degradation assessment.

e) List of corrective action documents generated by the vendor and/or site with respect to SG inspection activities.

- 8 - Enclosure B.5 Codes and Standards

a) Ready access to (i.e., copies provided to the inspector(s) for use during the inspection at the onsite inspection location, or room number and location where available):

i) Applicable Editions of the ASME Code (Sections V, IX and XI) for the inservice inspection program and the repair/replacement program.

ii) EPRI and industry standards referenced in the procedures used to perform the SGT eddy current examination.

Inspector Contact Information:

Ramon Azua Michael Bloodgood Senior Project Engineer Reactor Inspector

817-319-4376 817-276-6544 ray.azua@nrc.gov

michael.bloodgood@nrc.gov Mailing Address: US NRC Region IV

Attn: Ramon Azua 612 E. Lamar Blvd, Suite 400 Arlington, TX 76011