ML090760788
| ML090760788 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/17/2009 |
| From: | Hopper G NRC/RGN-II/DRS/EB3 |
| To: | Nazar M Florida Power & Light Co |
| References | |
| Download: ML090760788 (13) | |
Text
March 17, 2009 Mr. Mano Nazar Executive Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, FL 33408-0420
SUBJECT:
SAINT LUCIE NUCLEAR PLANT, UNIT 1 - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Nazar:
From May 11 to 15, 2009, the NRC will perform the baseline inservice inspection (ISI) at the Saint Lucie Nuclear Plant, Unit 1 (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 understand that our regulatory contact for this inspection will be Don Cecchett 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 Louis Lake at (404) 562-4683 (Louis.Lake@nrc.gov).
FP&L 2
In accordance with 10 CFR 2.390 of the NRC=s ARules 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).
Sincerely,
/RA/
George T. Hopper, Chief Engineering Branch 3 Division of Reactor Safety Docket No.: 50-335 License No.: DPR-DRP-67
Enclosure:
Pre-Inspection Document Request (cc w/encl: See page 3)
FP&L 3
cc w/encl:
Alison Brown Nuclear Licensing Florida Power & Light Company Electronic Mail Distribution Gordon L. Johnston Site Vice President St. Lucie Nuclear Plant Electronic Mail Distribution Michael Page Operations Manager (Acting)
St. Lucie Nuclear Plant Electronic Mail Distribution Robert J. Hughes Director Licensing and Performance Improvement Florida Power & Light Company Electronic Mail Distribution Christopher R. Costanzo Plant General Manager St. Lucie Nuclear Plant Electronic Mail Distribution Eric Katzman Licensing Manager St. Lucie Nuclear Plant Electronic Mail Distribution Abdy Khanpour Vice President Engineering Support Florida Power and Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Don E. Grissette Vice President, Nuclear Operations - South Region Florida Power & Light Company Electronic Mail Distribution M. S. Ross Managing Attorney Florida Power & Light Company Electronic Mail Distribution Marjan Mashhadi Senior Attorney Florida Power & Light Company Electronic Mail Distribution William A. Passetti, Chief Florida Bureau of Radiation Control Department of Health Electronic Mail Distribution Craig Fugate Director Division of Emergency Preparedness Department of Community Affairs Electronic Mail Distribution J. Kammel Radiological Emergency Planning Administrator Department of Public Safety Electronic Mail Distribution Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Ft. Pierce, FL 34982 Mano Nazar Senior Vice President and Nuclear Chief Operating Officer Florida Power & Light Company Electronic Mail Distribution Senior Resident Inspector St. Lucie Nuclear Plant U.S. Nuclear Regulatory Commission P.O. Box 6090 Jensen Beach, FL 34957-2010 Peter Wells (Acting) Vice President, Nuclear Training and Performance Improvement Florida Power and Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mark E. Warner Vice President Nuclear Plant Support Florida Power & Light Company Electronic Mail Distribution
FP&L 4
Letter to Mano Nazar from George Hopper dated March 17, 2009
SUBJECT:
ST. LUCIE PLANT - NRC INTEGRATED INSPECTION REPORT 05000335/2009 AND 05000389/2009 Distribution w/encl:
RIDSNRRDIRS PUBLIC B. Mozafari, NRR (PM: STL, TP)
Enclosure INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates:
May 11 to 15, 2009 Inspection Procedures:
IP 71111.08 Ainservice Inspection (ISI) Activities,@ issue date 10/4/2007 TI-2515/172, Reactor Coolant System Dissimilar Metal Butt Welds, issue date 2/21/2008 Inspectors:
Louis Lake, Sr. Reactor Inspector A.
Information Requested for the In-Office Preparation Week The following information should be sent to the Region II office in hard copy or electronic format (CD preferred), in care of Louis Lake by April 27, 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:
61 Nondestructive examinations (NDEs) planned for Class 1, 2 and 3 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 versus 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.
61 Reactor pressure vessel head (RPVH) examinations planned for the upcoming outage.
61 Examinations planned for Alloy 82/182/600 components that are not included in the Section XI scope, for example MRP-139.
iv)
Examinations planned as part of your Boric Acid Corrosion Control Program, for example Mode 3 walkdowns, bolted connection walkdowns, etc.
v)
Welding activities that are scheduled to be completed during the upcoming outage for ASME Class 1, 2, or 3 structures, systems, or components (SSCs).
2 Enclosure 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, and dye penetrant) which have identified surface or volumetric indications that were analytically evaluated and accepted for continued service 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. 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, and NDE performed) of the welds in Code Class 1, 2 or 3 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 or 10 CFR 50.55a 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) 61 Provide the detailed scope of NDE planned for the RPVH which identifies the types of NDE methods to be used on each specific part of the vessel head to meet the augmented inspection requirements of 50.55a(g)(6)(ii)(D).
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 industry or procedural standards which will be used to evaluate potential leakage and/or flaw indications).
c)
A list of identified surface or volumetric indications that were analytically evaluated and accepted for continued service in the RPVH penetration nozzles.
A.3 Boric Acid Corrosion Control Program (BACCP) a)
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
3 Enclosure 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 the unit was unexpectedly shutdown during the last operating cycle (e.g. a forced outage), 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.4 Steam Generator (SG) Inspections a)
A detailed schedule of:
i)
SG tube 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. Additionally, please provide a copy of EPRI Appendix H Eddy Current Technique Qualification Records.
61 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. (If applicable)
4 Enclosure 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 SG ISI examinations, including examination methods such as Bobbin, Rotating Pancake, or Plus Points, and the percentage of tubes to be examined. *Do not provide these documents separately if already included in other information requested.
A.5 Additional information related to all ISI activities a)
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 Unit 1 only). 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.
61 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 (May 11, 2009):
B.1 ISI / Welding Programs and Schedule Information a)
Updated schedules for ISI/NDE activities, including SG ISI, planned welding activities, and schedule showing contingency repair plans, if available.
b)
For welds selected by the inspector from Section A of this enclosure, please provide copies of the following documentation for each subject weld:
5 Enclosure 61 Weld data sheets and weld traveler 61 Weld configuration and system location iii)
Applicable Code Edition and Addenda for weldment iv)
Applicable Code Edition and Addenda for welding procedures 61 Applicable weld procedures (WPS) used to fabricate the welds vi)
Copies of procedure qualification records (PQRs) supporting the WPS from B.1.b.v 61 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 applicable 61 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 xii)
Copies of NDE personnel qualifications (VT, PT, UT, RT), as applicable c)
For the ISI related corrective action issues selected by the inspector from Section A of this enclosure, provide a copy of the corrective actions and supporting documentation.
d)
For the NDE reports with indications on Code Class 1 & 2 systems that were analytically evaluated for continued service selected by the inspector from Section A above, provide a copy of the examination records, examiner qualification records, associated corrective action documents, and supporting analysis.
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 NDE activities selected by the inspector from Section A of this enclosure, provide a 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 PDQS). 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.
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)
6 Enclosure 61 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% minimum coverage required by Code Case N-729-1 (if a visual examination is planned for the upcoming refueling outage).
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 and reinspection years (RIY).
g)
Provide copy of vendor reports which demonstrate the detection capability of NDE equipment used for the RPVH examinations. Also, identify any changes in equipment configuration used for the RPVH examinations which differ from that used in the vendor demonstration.
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 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 like to 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.4 Steam Generator (SG) 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.
7 Enclosure 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 operating experience communications such as Generic Letters, Information Notices, etc.
(As applicable to SG 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.
B.5 Codes and Standards a)
Ready access to (i.e. copies provided to the inspector to use for the duration of the inspection at the on-site inspection location, or room number and location where available):
61 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 SG tube eddy current examination.
Inspector Contact Information:
Louis Lake Sr. Reactor Inspector 404-562-4683 Louis.Lake@nrc.gov Mailing Address:
US NRC Region 2 Attn: Louis Lake 61 Forsyth Street SW, Suite 23T85 Atlanta, GA 30303
March 17, 2009 Mr. Mano Nazar Executive Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, FL 33408-0420
SUBJECT:
SAINT LUCIE NUCLEAR PLANT, UNIT 1 - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Nazar:
From May 11 to 15, 2009, the NRC will perform the baseline inservice inspection (ISI) at the Saint Lucie Nuclear Plant, Unit 1 (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 understand that our regulatory contact for this inspection will be Don Cecchett 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 Louis Lake at (404) 562-4683 (Louis.Lake@nrc.gov).
X SUNSI REVIEW COMPLETE OFFICE RII:DRS RII:DRS RII:DRP SIGNATURE
/RA/
/RA/
/RA/
NAME L. Lake G. Hopper M. Sykes DATE 3/17/2009 3/17/2009 3/17/2009 E-MAIL COPY?
YES NO YES NO YES NO YES NO YES NO YES NO YES NO