ML12199A295
| ML12199A295 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 07/06/2012 |
| From: | - No Known Affiliation |
| To: | Division of License Renewal |
| References | |
| Download: ML12199A295 (40) | |
Text
1 SeabrookNPEm Resource From:
Cliche, Richard [Richard.Cliche@fpl.com]
Sent:
Friday, July 06, 2012 1:55 PM To:
Cunanan, Arthur; Howard, Kent
Subject:
NextEra Seabrook ACRS slides Attachments:
7-6_ACRS Subcommittee Presentation without Notes.pdf Rick Cliche License Renewal Project Manager Seabrook Station richard.cliche@fpl.com Desk: (603) 773-7003 Fax: (603) 773-7995 Cell: (603) 765-6358
Hearing Identifier:
Seabrook_License_Renewal_NonPublic Email Number:
3250 Mail Envelope Properties (2B617A8F06E7124F9D8C7AE069F68EF91DAB785C05)
Subject:
NextEra Seabrook ACRS slides Sent Date:
7/6/2012 1:55:01 PM Received Date:
7/6/2012 1:57:38 PM From:
Cliche, Richard Created By:
Richard.Cliche@fpl.com Recipients:
"Cunanan, Arthur" <Arthur.Cunanan@nrc.gov>
Tracking Status: None "Howard, Kent" <Kent.Howard@nrc.gov>
Tracking Status: None Post Office:
GOXEXVS04.fplu.fpl.com Files Size Date & Time MESSAGE 199 7/6/2012 1:57:38 PM 7-6_ACRS Subcommittee Presentation without Notes.pdf 7206241 Options Priority:
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Recipients Received:
1 Seabrook Station Seabrook Station ACRS License Renewal Subcommittee ACRS License Renewal Subcommittee July 10, 2012 July 10, 2012
2 Personnel in Attendance Personnel in Attendance Kevin Walsh Site Vice President Jim Connolly Engineering Director Mike Collins Design Engineering Manager Mike Ossing Program Engineering Manager Mike OKeefe Licensing Manager Rick Noble Special Projects Manager Rick Cliche License Renewal Project Manager
3 Agenda Agenda
Background
- Plant
- Status
- Licensing License Renewal Project Overview
- Scoping
- Time Limited Aging Analysis
- Application of GALL
- Commitment Process SER Open Items
4 Background
Background --
Located in the Town of Seabrook, New Hampshire, two miles west of the Atlantic Ocean. Approximately two miles north of the Massachusetts state line and 15 miles south of the Maine state line.
Seabrook Station is a single unit Westinghouse 4-loop pressurized water reactor with a General Electric turbine generator.
Reactor housed in a steel lined reinforced concrete containment structure which is enclosed by a reinforced concrete containment enclosure structure.
3648 MWt Thermal Power; ~ 1,245 net megawatts electric The Atlantic Ocean is the normal ultimate heat sink.
Approximately 1100 people on site, including contractors.
5 Plant Site Plant Site
- Unit #2 Area
- Containment Building
- Waste Process Building
- Fuel Storage Building
- Control/Diesel Building
- Switchyard
- Turbine Building
- Primary Auxiliary Building
6 Licensing Licensing Construction Permit (CPPR-135)
July 1976 Zero Power Operating License (NPF-56)
October 1986 Low Power Operating License (NPF-67)
May 1989 Full Power Operating License (NPF-86)
March 15, 1990 Commercial Operation August 1990 Operating License Transfer to FPL Energy (NextEra)
November 2002 Stretch Power Uprate (3587 MW)
February 2005 Measurement Uncertainty Uprate (3648MW)
May 2006 LR Application Submitted May 25, 2010 Operating License Expires March 15, 2030
7 Plant Status Plant Status Cycle 15 - Refuel outage 14 completed in May 2011 Current Plant Status Next Refuel Outage - September 2012
8 License Renewal Project Overview License Renewal Project Overview Site Ownership and Oversight Experienced Team (Site, Corporate, Contract)
Benchmarking QA Audits Participation/Hosted industry working groups Industry Peer Review
9 Project Overview Project Overview -- Scoping Scoping Utilized site component database, controlled drawings, design and licensing documents SSCs Evaluated to Scoping Criteria 10CFR54.4 (a)(1), (a)(2) and (a)(3)
Identified SSCs that perform or support an intended function Non-Safety Affecting Safety (a)(2)
- Reviewed safety related equipment locations
- Conservative spaces approach
- Performed walk-downs for verification Use of commodity groups when evaluations were best performed by component type rather than SSC
10 Project Overview Project Overview -- TLAA TLAA Design and Licensing Basis reviewed for potential TLAAs Keyword Search (UFSAR, NUREG-0896, Calcs, Specs)
Review of previous LRA applications Neutron Fluence Determined fluence for operation to 60 years Materials in the extended beltline identified and evaluated Upper Shelf Energy values exceed the minimum acceptance limit of 50 ft-lbs PTS limits are below the maximum allowable screening criteria Metal Fatigue Cumulative Usage Factor evaluated for 60 years Environmentally Assisted Fatigue evaluated for NUREG/CR-6260 locations and weve committed to determine if these locations are limiting
11 Project Overview Project Overview -- GALL Application GALL Application 43 Aging Management Programs
- 29 Existing Programs
- 14 New Programs GALL Consistency
- 16 Consistent
- 11 Consistent with Enhancements
- 6 Consistent with Exceptions
- 4 Consistent with Exceptions and Enhancements
- 6 Plant Specific
-Buried Piping and Tank Inspection
-Boral Surveillance Program
-Nickel Alloy Nozzles and Penetrations
-SF6 Bus
-PWR Vessel Internals
-Alkali-Silica Reaction (ASR) Monitoring
12 Project Overview Project Overview -- Commitment Process Commitment Process 68 Regulatory Commitments for License Renewal Commitments entered into site commitment tracking system Implementation activities underway to ensure completion well in advance of PEO
13 SER Open Items
- 1. OI 3.0.3.2.2-1 Steam Generator Tube Integrity
- 2. OI 4.2.4-1 Pressure-Temperature Limit
- 3. OI 3.2.2.1-1 Treated Borated Water
- 4. OI 3.0.3.1.7-1 Bolting Integrity Program
- 5. OI B.1.4-2 Operating Experience
- 6. OI 3.0.3.1.9-1 ASME Section XI, IWE Program
- 7. OI 3.0.3.2.18-1 Structures Monitoring Program
14 Open Item Open Item -- Steam Generator Tube Integrity Program OI 3.0.3.2.2-1
- Cracking due to primary water stress corrosion cracking (PWSCC) on the primary coolant side of steam generator tube-to-tubesheet welds. Clarify commitment.
- Industry Experience (foreign) indicates potential degradation of steam generator divider plates. Commitment to inspect, but not included in UFSAR supplement.
Resolution
- LRA program has been enhanced to clarify the tube-to-tubesheet weld inspection commitment.
- LRA commitment to inspect steam generator divider plates has been added to the UFSAR supplement.
15 Open Item Open Item -- Pressure-Temperature Limit OI 4.2.4-1
- Consistency of methods used to develop the P-T limits with 10CFR50 Appendix G Resolution
- RAI expected under a separate licensing action. License Amendment Request (LAR) 11-06 requested approval to extend the current curves from 20 to 23.7 EFPY.
- Consistency with 10CFR50 Appendix G will be addressed via response to LAR 11-06 RAI.
16 Open Item -- Treated Borated Water OI 3.2.2.1-1
- LR-ISG-2011-01 recently issued with guidance for managing the aging effects of stainless steel structures and components exposed to treated borated water.
Resolution
- LRA updated to add affected components to the One Time Inspection Program population.
17 Open Item Open Item -- Bolting Integrity Program OI 3.0.3.1.7-1
- Once a seal cap enclosure is installed, the bolting and component external surfaces within the enclosure are no longer visible for direct inspection.
Resolution
- NextEra will remove the seal cap enclosure.
18 Open Item Open Item -- Operating Experience OI B.1.4-2
- Describe the programmatic details used to continually identify, evaluate and use Operating Experience.
Resolution
- LRA has been updated to document programmatic aspects of evaluating aging related OE and is being reviewed by the NRC Staff.
19 Open Item Open Item -- ASME Code Section XI, Subsection IWE Program OI 3.0.3.1.9-1
- Accumulation of water in the Containment Enclosure Building annular space can potentially degrade the containment liner plate.
ROCK BASE MAT LINER PLATE CONTAINMENT ENCLOSURE BUILDING ANNULUS EL-26 0
EL-30 0
CONCRETE CONTAINMENT BUILDING
20 Open Item Open Item -- ASME Code Section XI, Subsection IWE Program Resolution
- LRA updated to:
Perform confirmatory UT testing of the containment liner plate in the vicinity of the moisture barrier Implement measures to maintain the exterior surface of the Containment Structure, from elevation -30 feet to +20 feet, in a dewatered state.
21 Open Item Open Item -- Structures Monitoring Program OI 3.0.3.2.18-1
- Aging management of concrete structures affected by Alkali-Silica Reaction (ASR).
Resolution
- LRA updated to augment existing Structures Monitoring Program by addition of a plant specific Alkali-Silica Reaction (ASR)
Monitoring Program.
- The program is in effect and the extent of crack expansion is being monitored.
22 ASR - Background ASR identified in 1930s mostly in transportation industry and dams.
Assessments were made of 131 areas of the Plant.
23 ASR - Diagnosis Discovery made by petrographic examinations when concrete core samples were removed from below grade structures.
First core samples were removed in April and May 2010.
Testing revealed a reduction in modulus of elasticity.
Additional concrete core samples were removed from the same and five other structures to determine extent of condition.
Insights 1.
Areas affected were highly localized. Core samples taken from adjacent locations did not show signs of ASR.
2.
When the length of the cores were evaluated (i.e., depth into the wall) it was observed that the cracking was most severe at the exposed surface and reduced towards the center of the wall.
24 ASR - Structural Impact Confinement acts to restrain expansion of concrete similar to prestressing, thus improving performance of structural element.
Removed cores are tested in an unrestrained condition No direct correlation between mechanical properties of concrete cores and in situ properties of concrete.
Testing full scale structural elements provides more accurate concrete performance parameters.
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27 ASR - Prognosis What levels of ASR expansion are expected in the future ?
- Accelerated Expansion Testing Indicates reactive silica remains Tested rate not applicable to Seabrook structures
- Lack of confinement
- Severe exposure conditions
- Unrealistic specimen preparation (aggregate ground to sand)
- Monitoring the progression of ASR can be effectively accomplished by detailed visual inspections and trending of the observable surface of the structures.
- Crack mapping and expansion monitoring provides the best correlation to the progression of ASR in the structure.
28 ASR - Mitigation Strategies ASR can be effectively mitigated in fresh concrete by additions during batching.
ASR mitigation techniques for existing structures have been shown to be ineffective.
Stopping groundwater intrusion will not necessarily stop the progression of ASR.
29 ASR - Monitoring Program The Structures Monitoring Program, has been augmented by a plant specific Alkali-Silica Reaction (ASR) Monitoring Program.
- NUREG-1800 Appendix A.1, ten element review
- Guidelines in ACI 349.3R, Structural Condition Assessment of Buildings.
Action Levels developed based on available ASR guidance.
- Report on the Diagnosis, Prognosis, and Mitigation of Alkali-Silica Reaction in Transportation Structures, U.S. Dept. of Transportation, Federal Highway Administration, January 2010, Report Number FHWA-HIF-09-004.
- Structural Effects of Alkali-Silica Reaction: Technical Guidance on the Appraisal of Existing Structures, Institution of Structural Engineers, July 1992.
- ORNL/NRC/LTR-95/14, In-Service Inspection Guidelines for Concrete Structures in Nuclear Power Plants, December 1995.
30 ASR - Monitoring Program ASR detected by inspection of concrete structures by visual observation of cracking on the surface of the concrete. Baseline data collected.
Two parameters are used to monitor the extent and rate of ASR associated cracks. One is Cracking Index (CI) and the other is Individual Crack Width. Baseline data has been gathered.
Evaluation of a structures condition completed according to the guidelines set forth in the Structures Monitoring Program.
31 ASR - Monitoring Program Structural Monitoring Program Recommendation for Individual Concrete Components Combined Cracking Index CCI Individual Crack Width Tier 3 Structural Evaluation 1.0 mm/m or greater 1.0 mm or greater Tier 2 Quantitative Monitoring and Trending 0.5 mm/m or greater 0.2 mm or greater Qualitative Monitoring Any area with indications of pattern cracking or water ingress Tier 1 Routine inspection as prescribed by Structures Monitoring Program Area has no indications of pattern cracking or water ingress - No visual presence of ASR
32 ASR - Monitoring at Seabrook
June 2012
33 U-Texas-Plant Specific Testing Perform additional anchor testing using concrete blocks with design characteristics similar to Seabrook Station.
Large scale destructive testing of reinforced concrete beams with accelerated ASR will be conducted to determine the actual structural impact of ASR.
- Determine the actual structural impact of ASR
- Actions levels will be established based on correlation between the test results and observed expansion levels/crack indices.
Update ASR Monitoring Program with plant specific action levels.
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37 ASR-Conclusions The aging effects of ASR on Seabrook Station concrete structures is understood and manageable.
Monitoring the progression of ASR can be effectively accomplished by detailed visual inspections and trending of the observable surface of the structures.
Crack measurement provides the best correlation to the progression of ASR in the structure.
The Alkali-Silica Reaction (ASR) Monitoring Program provides reasonable assurance that structures will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.
38 Questions?