IR 05000301/2012008
| ML12355A774 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/19/2012 |
| From: | Ann Marie Stone NRC/RGN-III/DRS/EB2 |
| To: | Meyer L Point Beach |
| Stuart Sheldon | |
| References | |
| IR-12-008 | |
| Download: ML12355A774 (14) | |
Text
mber 19, 2012
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 2 NRC POST APPROVAL SITE INSPECTION FOR LICENSE RENEWAL INSPECTION REPORT 05000301/2012008
Dear Mr. Meyer:
On November 21, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed the outage segment of the Post-Approval Site Inspection for License Renewal at your Point Beach Nuclear Plant, Unit 2. The enclosed report documents the inspection activities, which were discussed on November 21, 2012, with you and other members of your staff.
This inspection was an examination of activities conducted under your renewed license as they relate to the completion of commitments made during the renewed license application process and compliance with the Commissions rules and regulations and the conditions of your operating license. Within these areas, the inspection involved examination of selected procedures and representative records, observations of activities, and interviews with personnel. On the basis of the sample selected for review, there were no findings of significance identified during this inspection. The NRC staff did not identify any instances of incomplete commitments with respect to timeliness or adequacy.
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) component of NRC's Agencywide Document Access and Management 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/
Ann Marie Stone, Chief Engineering Branch 2 Division of Reactor Safety Docket No. 50-301 License No. DPR-27
Enclosure:
Inspection Report 05000301/2012008 w/Attachment: Supplemental Information
REGION III==
Docket Nos: 05000301 License Nos: DPR-27 Report No: 05000301/2012008 Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant, Unit 2 Location: Two Rivers, WI Dates: November 5 - November 21, 2012 Inspectors: S. Sheldon, Senior Reactor Engineer (Lead)
A. Shaikh, Reactor Engineer Approved by: Ann Marie Stone, Chief Engineering Branch 2 Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 05000301/2012008; 11/5/2012 - 11/21/2012; Point Beach Nuclear Plant Unit 2;
Post-Approval Site Inspection for License Renewal.
The inspection was conducted by two regional based inspectors. No instances were noted of incomplete license renewal commitments with respect to timeliness or adequacy. No findings were identified by the inspectors. The significance of inspection findings are indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter (IMC) 0609, Significance Determination Process, dated June 2, 2011. Cross-cutting aspects are determined using IMC 0310, Components Within the Cross-Cutting Areas, dated October 28, 2011. All violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy dated June 7, 2012. 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.
NRC-Identified
and Self-Revealed Findings No findings were identified.
Licensee-Identified Violations
No violations were identified.
REPORT DETAILS
Summary of Plant Status
NextEra Energy Point Beach, LLC Unit 2 was in a refueling outage during the period of this inspection.
OTHER ACTIVITIES
4OA5 Other Activities
.1 Post-Approval Site Inspection for License Renewal (Phase I) - IP 71003
a. Inspection Scope
- (1) Review of Newly Identified Systems, Structures and Components (SSCs)
The inspectors discussed the identification of new SSCs, under the purview of Title 10 of the Code of Federal Regulations (CFR) 54.37(b), with the licensees license renewal staff. The licensee brought portions of the Primary Access Building (PAB) ventilation system into scope as a newly identified SSC during the license amendment process for Alternate Source Term. The licensee conducted an aging management review on the PAB ventilation system and incorporated the system into the Periodic Surveillance and Preventative Maintenance Aging Management Program.
The inspectors confirmed that the licensee had implemented preventative maintenance tasks consistent with aging management requirements for the PAB ventilation system.
In responding to inspector questions, the licensee identified the periodic update of the Final Safety Analysis Report (FSAR), submitted in June 2012, incorrectly stated the inclusion of the PAB ventilation system into License Renewal scope had been submitted in the previous years update. However, the licensee was not required to and therefore, did not submit a periodic update of the FSAR in 2011. The licensee submitted letter NRC 2012-0103 (ML12331A034) to revise the 2012 periodic FSAR update. The inspectors considered this omission a minor administrative issue.
- (2) Review of Revised Commitments As part of reviewing the aging management programs (AMPs) associated with the commitments, the inspectors determined that there were no commitment revisions within scope of the Phase I inspection.
- (3) Review of Commitments The inspectors reviewed supporting documents including completed surveillance records, conducted interviews, observed non-destructive examination (NDE) activities, performed visual inspection of structures and components, including those not accessible during power operation, and observed the activities described below to verity the licensee completed the necessary actions to comply with the license conditions that are a part of the renewed operating license. The inspectors verified the licensee implemented the outage related aging management programs included in NUREG-1839, Safety Evaluation Report (SER) related to the license renewal (LR) of the Point Beach Nuclear Plant, Unit 2, in accordance with 10 CFR Part 54, Requirements for the Renewal of Operating Licenses for Nuclear Power Plants.
b. Results of Detailed Reviews The inspectors reviewed portions of the commitments below, which are referenced to Appendix A of the SER. Activities observed related to these commitments are also listed. Specific documents reviewed are listed in the attachment.
- (1) American Society of Mechanical Engineers (ASME)Section XI, Subsections IWE and IWL Inservice Inspection Program (Commitment Item 14)
The ASME Section XI, Subsections IWE and IWL Inservice Inspection Program is an existing program that is consistent with NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Sections XI.S1, ASME Section XI, Subsection IWE, and XI.S4, 10 CFR Part 50 Appendix J, and is consistent with, but includes exceptions to,Section XI.S2, ASME Section XI, Subsection IWL. The ASME Section XI, Subsections IWE and IWL Inservice Inspection Program manages aging of:
- (a) steel liners of concrete containments and their integral attachments; containment hatches and airlocks; seals, gaskets and moisture barriers; and pressure retaining bolting, and
- (b) reinforced concrete containments and unbonded post-tensioning systems.
Commitment Item 14 states that the licensee will implement an enhanced ASME Section XI, Subsections IWE and IWL Inservice Inspection Program.
The inspectors reviewed photographic records of visual inspection of the containment liner. The inspectors also toured containment looking for degradation of the containment liner or any other visible components. The inspectors had no concerns with the observed activities.
- (2) Boric Acid Corrosion Program (Commitment Item 18)
The Boric Acid Corrosion Program is an existing program that is consistent with NUREG-1801 Section XI.M10, Boric Acid Corrosion. The program manages aging effects for structures and components as a result of borated water leakage. The program requires periodic visual inspection of systems that contain borated water for evidence of leakage or accumulations of dried boric acid. The program includes provisions for:
- (a) determination of principal location or source of leakage, (b)examination requirements and procedures for locating small leaks, and
- (c) evaluations and/or corrective actions to ensure that boric acid leakage does not lead to degradation of the leakage source as well as other SSCs exposed to the leakage, including mechanical, structural, and electrical items such as bolts, fasteners, piping, cables, cable trays, electrical connectors, etc., which could cause the loss of intended function(s).
This program complies with the requirements of NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components In PWR plants.
Commitment Item 18 states the licensee will implement and enhanced Boric Acid Corrosion Program.
The inspectors observed the bare metal visual examination of the reactor pressure vessel head surface for evidence of boric acid leakage. The inspectors also reviewed a sample of corrective action records from the previous and current refueling outages pertaining to identified boric acid leakage or buildup, and the boric acid corrosion evaluations associated with these identified boric acid leaks/deposits. The inspectors had no concerns with the observed and reviewed activities.
- (3) One-Time Inspection Program (Commitment Item 25)
The One-Time Inspection Program is consistent with, but includes exceptions to, NUREG-1801 Section XI.M32, One-Time Inspection, and Section XI.M33, Selective Leaching of Materials. The program addresses potentially long incubation periods for certain aging effects and provides a means of verifying that an aging effect is either not occurring or progressing so slowly as to have negligible effect on the intended function of the structure or component. Hence, the One-Time Inspection Program provides measures for verifying an aging management program is not needed, verifying the effectiveness of an existing program, or determining that degradation is occurring, which will require evaluation and corrective action.
Commitment Item 25 states that the licensee will develop and implement a One-Time Inspection Program. The initial scope of the program was completed prior to the period of extended operation for Unit 1; however, based upon licensee and industry operating experience, the licensee expanded the scope of the program to conduct additional inspections.
The inspectors reviewed the documented results of eddy current inspections of the Unit 2 Residual Heat Removal heat exchanger tubes, selective leaching inspections and visual inspections. The inspectors had no concerns with the observed activities.
- (4) Open-Cycle Cooling Water System Surveillance Program (Commitment Item 26)
The Open-Cycle Cooling (Service) Water (OCCW) System Surveillance Program is consistent with, but includes exceptions to, NUREG-1801 Section XI.M20, Open-Cycle Cooling Water System. The OCCW system surveillance program manages aging effects caused by exposure of internal surfaces of metallic components in water systems to raw, untreated water. The aging effects are managed through:
- (a) surveillance and control of biofouling,
- (b) verification of heat transfer by testing, and
- (c) routine inspection and maintenance program activities to ensure that aging effects do not impair component intended function.
Commitment Item 26 states that the licensee will implement an enhanced Open-Cycle Cooling (Service) Water System Surveillance Program.
The inspectors conducted interviews, observed visual inspections of the 2HX-015A containment fan cooler, and reviewed the implementing documents. The inspectors had no concerns with the observed activities.
- (5) Reactor Coolant System Alloy 600 Inspection Program (Commitment Item 28)
The Reactor Coolant System Alloy 600 (RCA 600) inspection program is a new program that is consistent with, but includes exceptions to, NUREG-1801,Section XI.M11, Nickel-Alloy Nozzles and Penetrations. The RCA 600 inspection program manages crack initiation and growth due to primary water stress corrosion cracking (PWSCC) of reactor coolant system (RCS) pressure boundary nickel-based alloy components (e.g.,
Alloy 600/690 reactor vessel/head penetration nozzles, Inconel 82/182, 82/152, and 52/152 weld joints). The program includes:
- (a) PWSCC susceptibility assessment using industry models to identify susceptible components,
- (b) monitoring and control of reactor coolant chemistry to mitigate PWSCC,
- (c) inservice inspection of reactor vessel/head penetrations and RCS pressure boundary welds in accordance with ASME Section XI, Subsection IWB, Table IWB 2500-1, and
- (d) augmented inspections or pre-emptive repair/replacement of susceptible components or welds.
Commitment Item 28 states the licensee will develop and implement a Reactor Coolant System Alloy 600 Inspection Program.
The inspectors observed and reviewed the ultrasonic examination and eddy current testing of the Unit 2 Steam Generators nozzle to safe-end alloy 600 dissimilar metal welds. The inspectors had no concerns with the observed and reviewed activities.
- (6) Steam Generator Integrity Program (Commitment Items 31, 50 and 68)
The Steam Generator Integrity Program is consistent with NUREG-1801,Section XI.M19, Steam Generator Tube Integrity, with regards to managing the aging effects of steam generator (SG) tubes, and tube plugs or other tube repairs. The Steam Generator Integrity Program incorporates the Guidance of NEI 97-06 Steam Generator Program Guidelines, and maintains the integrity of the SGs, including tubes, tube plugs or other tube repairs, and various secondary-side internal components. The program manages aging effects through a balance of prevention, inspection, evaluation, repair, and leakage monitoring measures.
Commitment Item 31 states that the licensee will implement an enhanced Steam Generator Integrity Program. Commitment Item 50 states in part that [a]s part of the Steam Generator Integrity Program, visual inspections of accessible areas to verify the integrity of steam generator secondary-side components will be performed at least every six years, with one steam generator being inspected every three years on an alternating basis. Any indications of degradation or unacceptable conditions will be evaluated through the corrective action program, including the extent of condition. Commitment Item 68 states the licensee will age manage the steam generator feedrings, J-nozzles, and feedring supports using the Water Chemistry Control Program and the Steam Generator Integrity Program.
The inspectors conducted interviews, observed visual inspections of the steam side of the 2HX-1A and 2HX-1B steam generators, eddy current testing and analysis of the Unit 2 steam generator tubes, and reviewed the implementing documents. The inspectors had no concerns with the observed activities.
- (7) Structures Monitoring Program (Commitment Item 32)
The Structures Monitoring Program is consistent with NUREG-1801, Sections XI.S5, Masonry Wall Program, and XI.S6, Structures Monitoring Program, and is consistent with, but includes exceptions to, Sections XI.S7, RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants, and XI.M23, Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems. The Structures Monitoring Program manages the aging effects associated with steel (including fasteners), concrete (including masonry block and grout), earthen berms, and elastomers. The environments include below grade and fluid exposed material, outdoor weather, and indoor air.
Commitment Item 32 states that the licensee will implement an enhanced Structures Monitoring Program.
The inspectors reviewed documentation and video records of underwater inspections of the Unit 2 Forebay, Service Water Bay, and Travelling Screen Bays. The inspectors had no concerns with the observed activities.
4OA6 Management Meetings
.1 Exit Meeting Summary
On November 21, 2012, the inspectors presented the inspection results by telephone to Mr. Larry Meyer and other members of the licensee staff. The licensee acknowledged the issues presented. The inspectors confirmed that none of the potential report input discussed was considered proprietary.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- L. Meyer, Site Vice President
- B. Woyak, Program Engineering Manager
- E. Schmidt, Program Engineering Supervisor
- T. D. Mielke, License Renewal Engineer
- S. Forsha, Program Engineer
- M. Miller, Licensing Manager
- B. Scherwinski, Licensing
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened, Closed and
Discussed
None Enclosure