ML070820275

Request for Information, Notification of Inspection

ML070820275
Person / Time
Site:	Robinson
Issue date:	03/23/2007
From:	Hopper G NRC/RGN-II/DRS/EB3
To:	Walt T Carolina Power & Light Co
References
Download: ML070820275 (12)

Text

March 23, 2007Carolina Power and Light CompanyATTN:Mr. T. D. WaltVice PresidentH. B. Robinson Steam Electric Plant Unit 2 3581 West Entrance Road Hartsville, SC 29550

SUBJECT:

ROBINSON NUCLEAR PLANT, UNIT 2 - NOTIFICATION OF INSPECTIONAND REQUEST FOR INFORMATION

==Dear

Dear Mr.Walt:

==

From April 16 to April 27, 2007, the NRC will perform the baseline inservice inspection (ISI) atthe Robinson Nuclear Plant, Unit 2 (NRC Inspection Procedure 71111.08. Experience has shown that this inspection is resource intensive both for the NRC inspectors and your staff. In order to minimize the impact to your on-site 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) identifies 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 for these inspection activities with your staff and understandthat our regulatory contact for this inspection will be Garrett Sanders of your 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 Alexandra Vargas-Mendez (Rogers) at (404) 562-4657 (aav@nrc.gov).In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosure will be available electronically for public inspection in the NRC PublicDocument 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).Sincerely,/RA/George T. Hopper, ChiefEngineering Branch 3 Division of Reactor SafetyDocket No. 50-261 License No. DPR-23

Enclosure:

INSERVICE INSPECTION DOCUMENT REQUEST CP&L2cc w/encl:William G. Noll Director, Site Operations Carolina Power & Light Company H. B. Robinson Steam Electric Plant Electronic Mail DistributionErnest J. Kapopoulos, Jr.Plant General Manager Carolina Power & Light Company H. B. Robinson Steam Electric Plant Electronic Mail DistributionPaul Fulford, ManagerPerformance Evaluation and Regulatory Affairs PEB 5 Electronic Mail DistributionC. T. Baucom, SupervisorLicensing/Regulatory Programs Carolina Power & Light Company H. B. Robinson Steam Electric Plant Electronic Mail DistributionJ. F. Lucas, ManagerSupport Services - Nuclear Carolina Power & Light Company H. B. Robinson Steam Electric Plant Electronic Mail DistributionHenry J. Porter, DirectorDiv. of Radioactive Waste Mgmt.

Dept. of Health and Environmental Control Electronic Mail DistributionR. Mike GandyDivision of Radioactive Waste Mgmt.

S. C. Department of Health and Environmental Control Electronic Mail DistributionBeverly Hall, Chief RadiationProtection Section N. C. Department of Environment, Health and Natural Resources Electronic Mail DistributionDavid T. ConleyAssociate General Counsel - Legal Dept.

Progress Energy Service Company, LLC Electronic Mail DistributionJohn H. O'Neill, Jr.Shaw, Pittman, Potts & Trowbridge 2300 N. Street, NW Washington, DC 20037-1128Chairman of the North Carolina Utilities Commission c/o Sam Watson, Staff Attorney Electronic Mail DistributionRobert P. GruberExecutive Director Public Staff - NCUC 4326 Mail Service Center Raleigh, NC 27699-4326Public Service CommissionState of South Carolina P. O. Box 11649 Columbia, SC 29211

_________________________OFFICERII:DRSRII:DRSSIGNATURE/RA//RA/NAMEA. VargasG. HopperDATE3/23/2007March 27, 2007March 27, 2007March 27, 2007March 27, 2007March 27, 2007March 27, 2007 E-MAIL COPY? YESNO YESNO YESNO YESNO YESNO YESNO YESNO CP&L3Letter to: Mr. T. D. Walt, Robinson Nuclear Plant Dated: March 23, 2007Distribution w/encl

C. Patel, NRR C. Evans (Part 72 Only)

L. Slack, RII EICS OE Mail (email address if applicable)

RIDSNRRDIRS PUBLIC EnclosureINSERVICE INSPECTION DOCUMENT REQUESTInspection Dates:April 16-27, 2007Inspection Procedures:IP 71111.08 "Inservice Inspection (ISI) Activities"Inspectors:Alexandra Vargas-Mendez (Rogers), Reactor Inspector (LeadInspector - ISI/SGISI)A.Information Requested for the In-Office Preparation WeekThe following information should be sent to the Region II office in hard copy orelectronic format (CD preferred), in care of Alexandra Vargas-Mendez by April 9, 2007, 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. *Pleaseprovide requested documentation electronically if possible. If requested documents arelarge and only hard copy formats are available, please inform the inspector, and providesubject documentation during the first day of the onsite inspection. If you have anyquestions regarding this information request, please call the inspector as soon as

possible.A.1ISI / Welding Programs and Schedule Informationa)A detailed schedule (including preliminary dates) of:i) Nondestructive examinations (NDEs) planned for Class 1 & 2 systemsand 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 theupcoming outage.iii) Examinations planned for Alloy 82/182/600 components that are notincluded in the Section XI scope. (If applicable)iv)Examinations planned as part of your Boric Acid Corrosion ControlProgram (Mode 3 walkdowns, bolted connection walkdowns, etc.)

2Enclosurev)Welding activities that are scheduled to be completed during theupcoming 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 SafetyEvaluations applicable to the examinations identified above. c)A list of NDE reports (ultrasonic, radiography, magnetic particle, dye penetrant,visual VT-1, VT-2, and VT-3) which have identified recordable indications(geometric or flaw) on Code Class 1 & 2 systems since the beginning of the last refueling outage. Also, include in the list the NDE reports with recorded indications 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 recordable indication was identified.d)A list with a brief description (e.g. system, material, pipe size, weld number, andNDE 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 scheduledto 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 ofSection 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.2Reactor Pressure Vessel Head (RPVH) a) Provide the detailed scope of the planned NDE of the reactor vessel head whichidentifies the types of NDE methods to be used on each specific part of the vessel head to fulfill NRC commitments made in response to NRC Bulletin 2002-02 and NRC Order EA-03-009. Also, include examination scope expansion criteria and planned expansion sample sizes if relevant indications are identified.

(If applicable)b) A list of the standards and/or requirements that will be used to evaluateindications identified during NDE of the reactor vessel head (e.g. the specific industry or procedural standards which will be used to evaluate potential leakage and/or flaw indications).

3EnclosureA.3Boric Acid Corrosion Control Program (BACCP)a) Copy of the procedures that govern the scope, equipment and implementation ofthe 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 havebeen 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 walk-down inspections performed as part of the

BACCP.c)Please provide a copy of the most recent self-assessment performed for the BACCP.A.4Steam Generator (SG) Inspectionsa)A detailed schedule of:i) SG tube inspection, data analyses, and repair activities for the upcomingoutage. (If occurring)ii) SG secondary side inspection activities for the upcoming outage. (Ifoccurring)b)Please provide a copy of your SG ISI Inspection Program and Plan. Pleaseinclude a copy of the Operational Assessment from last outage, and a copy of the following documents as they become available: i)Degradation Assessmentii)Condition Monitoring Assessment c)If you are planning on modifying your Technical Specifications such that they areconsistent 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 EddyCurrent Technique. Additionally, please provide a copy of EPRI Appendix H Eddy Current Technique Qualification Records.f)Identify and quantify any SG tube leakage experienced during the previousoperating cycle. Also provide documentation identifying which SG was leaking and corrective actions completed or planned for this condition. (If applicable) 4Enclosureg) Provide past history of the condition and issues pertaining to the secondary sideof 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 SGmonitoring, loose parts monitoring, and secondary side water chemistry control programs.i)Please also indicate where the primary, secondary, and resolution analyses arescheduled to take place.j)Please provide a summary of the scope of the SG ISI examinations, includingexamination methods such as Bobbin, Rotating Pancake, or Plus Points, and the percentage of tubes to be examined. *Do not provide these documentsseparately if already included in other information requested. A.5Additional information related to all ISI activitiesa) A list with a brief description of ISI, BACCP, and SG ISI 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/SG tube 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 on-site to the inspector at the entrance meeting(April 16, 2007):B.1ISI / Welding Programs and Schedule Informationa)Updated schedules for ISI/NDE activities, including SG ISI, planned weldingactivities, and schedule showing contingency repair plans, if available.

5Enclosureb)For ASME Class 1 and 2 welds selected by the inspector from the lists providedfrom 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 WPSfrom B.1.b.vvii)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 allowviewing radiographs (If RT was performed)x)Copies of the preservice examination records for the selected welds.

xi)Copies of welder performance qualifications records applicable to WPS,including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS (At least six months prior to date subject work)xii)Copies of NDE personnel qualifications (VT, PT, UT, RT) As applicablec)For the ISI related corrective action issues selected by the inspector from sectionA of this enclosure, provide a copy of the corrective actions and supporting documentation.d)For the NDE reports with recordable indications on Code Class 1 & 2 systemsselected 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 Manualand Plan for the current Interval. f)For the NDEs selected by the inspector from section A of this enclosure, providecopy 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 documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers) and NDE personnel qualification records.

6EnclosureB.2Boric Acid Corrosion Control Program (BACCP)a)Please provide boric acid walk down inspection results, an updated list of boricacid 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 leaksidentified 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 specify which known leaks, if any, have remained in service or will remain in service as active leaks. c) In accordance with NRC inspection procedure 71111.08, the inspector would liketo conduct an independent boric acid walk down of the Reactor Building early in the inspection week. Please have knowledgeable BACCP staff available to accompany the inspector during the walk down.B.3Steam Generator (SG) Inspectionsa)Copies of the Examination Technique Specification Sheets (ETSS) andassociated justification for any revisions.b)Copy of the guidance to be followed if a loose part or foreign material is identifiedin the SGs.c)Please provide a copy of the ET procedures used to perform the SG ISI(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 operatingexperience communications such as Generic Letters, Information Notices, etc.

(As applicable to SG inspections) *Do not provide these documents separately ifalready included in other information requested such as the degradation

assessment.e)List of corrective action documents generated by the vendor and/or site withrespect to SG inspection activities.B.4Codes and Standards a)Ready access to: (i.e. copies provided to the inspector to use for the duration ofthe inspection at the on-site inspection location, or room number and location where available) i) Applicable editions of the ASME Code (Sections V, IX and XI) for theinservice inspection program and the repair/replacement program. ii) EPRI and industry standards referenced in the procedures used toperform the SG tube eddy current examination.

7EnclosureInspector Contact Information

Alexandra Vargas-Mendez (Rogers)Reactor Inspector 404-562-4825 jer6@nrc.govMailing Address

US NRC Region 2 Attn: Alexandra Vargas-Mendez 61 Forsyth Street SW, Suite 23T85 Atlanta, GA 30303