IR 05000250/2012007
| ML12089A040 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/29/2012 |
| From: | Vias S J NRC/RGN-II/DRS/EB3 |
| To: | Nazar M Florida Power & Light Co |
| Linda Gruhler 404-997-4614 | |
| References | |
| IR-12-007 | |
| Download: ML12089A040 (12) | |
Text
March 29, 2012
Mr. Mano Nazar Executive Vice President and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, FL 33408-0420
SUBJECT: TURKEY POINT NUCLEAR PLANT - NRC POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL INSPECTION REPORT 05000250/2012007
Dear Mr. Nazar:
On March 2, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed a Post-Approval Site Inspection for License Renewal at your Turkey Point Nuclear Plant, Unit 3. The enclosed report documents the inspection results, which were discussed on March 2, 2012, with you and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspector reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings were identified. The inspectors determined that the overall implementation of Aging Management Program activities reviewed during the Unit 3 refueling outage was consistent with the License Renewal commitments In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its Enclosure, and your response (if any), will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS)
2 FP&L component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,/RA/ Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-250 License Nos. DPR-31
Enclosure:
Inspection Report 05000250/2012007
w/Attachment:
Supplemental Information
cc w/encl: (See page 3)
2 FP&L component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,/RA/ Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-250 License Nos. DPR-31
Enclosure:
Inspection Report 05000250/2012007
w/Attachment:
Supplemental Information
cc w/encl: (See page 3) Distribution w/encl: C. Evans, RII EICS (Part 72 Only) L. Douglas, RII EICS (Linda Douglas) OE Mail (email address if applicable) RIDSNRRDIRS PUBLIC RidsNrrPMTurkeyPoint Resource X PUBLICLY AVAILABLE G NON-PUBLICLY AVAILABLE G SENSITIVE X NON-SENSITIVE ADAMS: X Yes ACCESSION NUMBER: ML12089A040 X SUNSI REVIEW COMPLETE X FORM 665 ATTACHED OFFICE RII:DRS/EB3 RII:DRS/EB3 RII:DRS/EB3 RII:DRP/BR3 SIGNATURE /RA/ /RA via email/ /RA/ /RA/ NAME R. Williams J. Rivera-Ortiz S. Vias D. Rich DATE 3/ 27 /2012 3/ 27 /2012 3/ 27 /2012 3/ 27 /2012 E-MAIL COPY YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: S:\DRS\ENG BRANCH 3\INSPECTIONS\INSPECTION AREAS\LICENSE RENEWAL\TURKEY POINT\TURKEY POINT 71003-
PHASE 1 IR 2012-007 - REW.DOCX
3 cc w/encl: Alison Brown Nuclear Licensing Florida Power & Light Company Electronic Mail Distribution Larry Nicholson Director Licensing Florida Power & Light Company Electronic Mail Distribution Michael Kiley Site Vice President Turkey Point Nuclear Plant Florida Power and Light Company Electronic Mail Distribution Niel Batista Emergency Management Coordinator Department of Emergency Management and Homeland Security Electronic Mail Distribution Robert J. Tomonto Licensing Manager Turkey Point Nuclear Plant Florida Power & Light Company Electronic Mail Distribution Eric McCartney Plant General Manager Turkey Point Nuclear Plant Florida Power and Light Company Electronic Mail Distribution Mitch S. Ross Vice President and General Counsel Nuclear 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 Senior Resident Inspector Turkey Point Nuclear Generating Station U.S. Nuclear Regulatory Commission 9762 SW 344th St. Florida City, FL 33035 Attorney General Department of Legal Affairs The Capitol PL-01 Tallahassee, FL 32399-1050 County Manager of Miami-Dade County 111 NW 1st Street, 29th Floor Miami, FL 33128 Gene St. Pierre Vice President, Fleet Support Florida Power & Light Company Electronic Mail Distribution George Gretsas City Manager City of Homestead Electronic Mail Distribution Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION II Docket Nos: 50-250 License Nos: DPR-31 Report No: 05000250/2012007 Licensee: Florida Power & Light Company (FPL)
Facility: Turkey Point Nuclear Plant, Unit 3 Location: 9760 S. W. 344th Street Homestead, FL 33035 Dates: February 27 - March 2, 2012 Inspectors: Robert Williams Jr., Reactor Inspector Approved by: Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety
SUMMARY OF FINDINGS
IR 05000250/2012007; 02/27/2012 - 03/02/2012; Turkey Point Nuclear Plant Unit 3; Post Approval Site Inspection for License Renewal. The report covers an inspection conducted by a regional inspector in accordance with NRC Manual Chapter 2515 and NRC Inspection Procedure 71003, Post-Approval Site Inspection for License Renewal.
Based on the sample selected for review, the inspector determined that commitments, license conditions, and regulatory requirements associated with the renewed facility operating license were either being met or, where commitment actions had not been completed, the licensee had administrative controls in place to ensure completion before the period of extended operation.
The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006. A. NRC-Identified and Self-Revealed Findings None
B. Licensee-Identified Violations
None
REPORT DETAILS
OTHER ACTIVITIES
4OA5 Other Activities
.1 Post-Approval Site Inspection for License Renewal - IP 71003 (Phase 1)
a. Inspection Scope
(1) Implementation of License Conditions and Commitments, including Aging Management Programs The inspector reviewed a sample of license renewal activities scheduled for the Unit 3 spring 2012 refueling outage, which was the last outage before the beginning of the period of extended operation (PEO). The inspectors selected this refueling outage because it would present the best opportunity to observe the majority of the one-time inspections associated with license renewal commitments. The inspection's objective was to maximize observations of the actual implementation of license renewal activities before the beginning of the PEO (July 12, 2012), and verify that the licensee completed the necessary actions to: (a) comply with the conditions stipulated in the renewed facility operating license; (b) meet the license renewal commitments described in NRC Memorandum dated March 6, 2007 (ADAMS Accession Number ML070640041), and (c)meet the future inspection activities described in the Updated Final Safety Analysis Report (UFSAR) supplement submitted pursuant to 10 CFR 54.21(d). The license renewal application (LRA) for Turkey Point Nuclear Plant, Units 3 & 4, and the corresponding NRC Safety Evaluation Report (SER) documented in NUREG-1759 are publicly available on ADAMS under accession numbers ML003764392 and ML021280541, respectively.
The inspectors reviewed supporting documents; conducted interviews with licensee staff; observed in-process outage activities; and performed visual inspection of structures, systems, and components (SSCs) including those not accessible during power operation. The specific inspection activities conducted for each Aging Management Programs (AMPs) are also described below. Specific documents reviewed are listed in the report Attachment.
Item 4 - Field Erected Tanks Internal Inspection Commitment Item 4 in the NRC Memorandum dated March 6, 2007, specified that a one-time visual inspection of the field erected tanks for both units (including the condensate storage tanks, the demineralized water storage tank and the refueling water storage tanks) will be performed on their internal surfaces. These inspections were to be completed prior to the end of the initial operating license term. As described in the licensee's Updated Final Safety Analysis Report (UFSAR), the results of these inspections would be evaluated to determine the need for additional inspections/programmatic corrective actions. The examination of field erected tanks consisted of one-time visual inspections that would ensure that the loss of material aging effect was identified before there was a loss of intended function. The scope of the examinations was to include all accessible internal surfaces of the above mentioned tanks. The visual inspections monitored for evidence of flaking, blistering, peeling, discoloration, pitting, or excessive corrosion of the internal tank surfaces. The inspector reviewed the licensing basis, implementing procedures, engineering evaluations, the results of previous visual examinations performed on four of the field erected tanks, as well as the non-destructive examination planned for the visual inspection of the Unit 3 condensate storage tank, to verify that the examinations were being implemented as stated in the commitment. Item 15 - Systems and Structures Monitoring Program Commitment Item 15 in the NRC Memorandum dated March 6, 2007, specified that the Systems and Structures Monitoring Program will be enhanced by restructuring it to address inspection requirements to manage certain aging effects, in accordance with 10 CFR 54, modifying the scope of specific inspections and improving documentation requirements. NUREG-1759, and the UFSAR supplement for license renewal, described the planned inspections, scope changes, and enhancements for this program.
The examination of the structures and systems within the scope of the Systems and Structures Monitoring Program consists of visual examinations (VT-1 and VT-3) performed in accordance Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. This program was credited to manage loss of material, cracking, fouling, loss of seal and change in materials properties for the systems, structures and components within its scope. Aging management of structural components that were inaccessible for inspection was accomplished by inspecting accessible structural components with similar materials and environments for aging effects that may be indicative of aging effects for the inaccessible structural components.
The inspector reviewed the licensing basis, implementing procedures, engineering evaluations, personnel qualifications, and non-destructive examination plans to verify that the Systems and Structures Monitoring examinations performed during the spring 2012 outage were implemented as stated in the commitment. Additionally, the inspector directly observed the VT-3 examination of the 58' level of containment (which included all accessible structures and containment surfaces) to verify that essential attributes, such as calibration and disposition of indications, were performed in accordance with the license renewal commitment. UFSAR Section 16.2.1.2, ASME Section XI, Subsection IWE Inservice Inspection Program This section of the UFSAR supplement specified that the existing ASME Section XI, Subsection IWE program would be credited to identify and correct degradation of pressure retaining components and their integral attachments, and the metallic line of Class CC pressure-retaining components and their integral attachments. This program managed the aging effects of loss of material and loss of pressure retention. The inspector directly observed visual examinations (VT-1) of the containment moisture barrier, reviewed the licensing basis, implementing procedures, equipment calibration, and personnel qualifications to verify that the examination was performed as described in the UFSAR.
UFSAR Section 16.2.1.3, ASME Section XI, Subsection IWE Inservice Inspection Program This section of the UFSAR supplement specified that the existing ASME Section XI, Subsection IWF program would be credited to identify and correct degradation of ASME Class 1, 2 and 3 component supports. This program managed the aging effect of loss of material.
The inspector directly observed visual examinations (VT-1 and VT-3) of component supports for the non-regenerative heat exchangers and double acting restraints for components in the component cooling water system. The inspector reviewed the licensing basis, implementing procedures, equipment calibration, and personnel qualifications to verify that the examination was performed as described in the UFSAR. (2) Review of License Renewal Commitment Changes The inspector reviewed license renewal commitment change documents to verify the licensee followed the guidance in Nuclear Energy Institute (NEI) 99-04, "Guidelines for Managing NRC Commitment Changes," for any changes made to Commitment Items 4, 6, and 7. The inspector verified that the licensee properly evaluated, reported, and approved where necessary, changes to license renewal commitments listed in the UFSAR in accordance with 10 CFR 50.59. Specifically, the inspector reviewed the change to the lighting requirements for the inspection of field erected storage tanks, the change to the implementation schedule for the Reactor Vessel Internals Inspection Program, and the intent to now follow the guidance provided in the Generic Aging Lessons Learned (GALL) Report, NUREG-1801, Rev. 2, Section AMP XI.M35, "One-Time Inspection of ASME Code Class 1 Small-Bore Piping." The inspector did not identify any examples where commitment changes were not consistent with the guidance in NEI 99-04. The review of remaining license renewal commitment changes is scheduled to be completed during the Phase 2 implementation of inspection procedure 71003. (3) Review of Newly Identified SSCs The review of newly identified SSCs pursuant 10 CFR 54.37(b) is scheduled to be completed during the Phase 2 implementation of inspection procedure 71003. (4) Review of the Description of AMPs and TLAAs in the UFSAR Supplement The review of the description of AMPs and TLAAs in the UFSAR supplement submitted pursuant 10 CFR 54.21(d) is scheduled to be completed during the Phase 2 implementation of inspection procedure 71003.
b. Findings and Observations
No findings or observations were identified.
4OA6 Management Meetings
.1 Exit Meeting Summary On March 02, 2012, the inspector presented the inspection results to Mr. Kiley and other members of the licensee staff.
The licensee acknowledged the inspection results. The inspector confirmed that all proprietary information reviewed during the inspection was returned to the licensee and that none of the potential report input discussed was considered proprietary. ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- D. Patel, License Renewal Group
- K. Mohindral, FPL License Renewal Manager
- R. Earl, License Renewal Group Lead
- S. Mihalakea, FPL Licensing
LIST OF REPORT ITEMS
None
LIST OF DOCUMENTS REVIEWED
Procedures
- 0-ADM-561, Structures Monitoring Program, Rev. 1
- 0-ADM-564, Systems Programs Monitoring, Rev. 0 NDE 4.1, Component, Support & Inspection Visual Examination
- VT-1 Welds/Bolting/Bushings/Washers, Rev. 13 NDE 4.3, Component, Support & Inspection Visual Examination
- VT-3, Rev. 11 NDE 4.7, Component, Support & Inspection Visual Examination of Reactor Building Containment Vessel General Visual/Detailed Visual (VT-1)/VT-3, Rev. 4
- Corrective Actions Documents
- AR 01739849, Conduit rubbing SI test line adjacent to 3-877B check valve
- AR 01739989, Tracking structures monitoring inspections
- AR 01740020, 0-ADM-561 - Structures monitoring program
- NCR 88-0021, Support upstream of valve 3-876B
Drawings
- 5613-H-631, Component Cooling Water System (I.C.) Stress Problem
- CCW-33, Sheet 12A, Rev. 1 5613-H-631, Component Cooling Water System (I.C.) Stress Problem
- CCW-33, Sheet 12B, Rev. 1 5613-H-631, Component Cooling Water System (I.C.) Stress Problem
- CCW-33, Sheet 12C, Rev. 1 5613-P-623-S, Component Cooling Water System, System No. 30 Outside Containment Stress Problem
- CCW-10, Rev. 1
Other Documents
- Field Erected Tanks Internal Inspection, Spec-C-047, Rev. 1 L-2011-265, Letter from M. Kiley to U.S. Nuclear Regulatory Commission, Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 License Renewal One-Time Inspection of Class 1 Small Bore Piping Program Revised Commitment and Inspection Plan Submittal
- L-2011-385, Letter from M. Kiley to U.S. Nuclear Regulatory Commission, Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 License Renewal Commitment Change Summary L-2011-531, Letter from M. Kiley to U.S. Nuclear Regulatory Commission, Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 License Renewal Reactor Vessel Internals
(RVI) Inspection Program Implementation Commitment Revision Notification
- LMT-QA-46, Personnel Certification Statement for: T. Moore, J. Block and J. Timm
- NUREG-1759, Safety Evaluation Report Related to the License Renewal of Turkey Point Nuclear Plant Units 3 and 4, with Supplement 1 Turkey Point Nuclear Plant Units 3 and 4 Updated Final Safety Analysis Report, Chapter 16
- Visual Examination Record (VT-3) Mechanical and Welded Attachments, Data Sheet# 4.1-001, 4.3-001, 4.3-002, 4.7-001, 4.7-002, 4.7-003, 4.7-004, 4.7-005, 4.7-006 Work Order
- 39022011-01, Unit 3 RWST Internal Tank Inspection Work Order
- 39022012-01, Unit 4 RWST Internal Tank Inspection Work Order
- 39022126-01, Unit 4 CST Internal Tank Inspection Work Order
- 40005208-01, License Renewal Internal Inspection DWST