ML12097A216
| ML12097A216 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/05/2012 |
| From: | Mathews T P Morgan, Morgan, Lewis & Bockius, LLP, FirstEnergy Nuclear Operating Co |
| To: | Froehlich W J, Kastenberg W E, Trikouros N G Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| RAS 22224, 50-346-LR, ASLBP 11-907-01-LR-BD01 | |
| Download: ML12097A216 (29) | |
Text
Timothy P. Matthews Partner 202.739.5527 tmatthews@morganlewis.com Morgan, Lewis & Bockius LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004
Tel. 202.739.3000 Fax: 202.739.3001 www.morganlewis.com April 5, 2012 William J. Froehlich, Chair Nicholas G. Trikouros Dr. William E. Kastenberg Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Docket: FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station, Unit 1, Docket No. 50-346-LR Re: Notification of Filing Related to Proposed Shield Building Cracking Contention
Dear Licensing Board Members:
The purpose of this letter is to provide notification that FirstEnergy Nuclear Operating Company (FENOC), applicant in this proceeding, sent the enclosed letter to the Nuclear Regulatory Commission (NRC) today. The letter provides FENOCs response to the NRC Staffs December 27, 2011 Request for Additional Information (RAI) B.2.39-13 regarding Shield Building cracking. The RAI response identifies revisions to the Davis-Besse License Renewal Application. FENOC is notifying the Board of the enclosed letter because it is relevant to the proposed contention that was filed by the Intervenors on January 10, 2012 in this proceeding. Respectfully submitted, Executed in Accord with 10 C.F.R. § 2.304(d)
Signed (electronically) by Timothy P. Matthews Timothy P. Matthews
Counsel for FENOC Enclosure cc: Service List
Enclosure 1
Attachment L-12-028Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), License Renewal Application, Section B.2.39 Page 1 of 8 Section B.2.39 Question RAI B.2.39-13
Background:
In order to perform a scheduled reactor head replacement, a construction opening was made in the concrete shield building. During hydro-demolition of the concrete shield building, cracks were identified in the architectural shoulders of
the shield building. While investigating the extent of the cracking, additional cracks were identified around the shield building. These additional cracks were identified using an Impulse Response (IR) technique and core bores were used to verify the IR results.
Issue:Extensive cracking in the shield building could affect the structural integrity of the shield building and may impact its ability to perform its intended function
during the period of extended operation.
Request:1. Summarize the shield building degradation, the root cause, and the expected corrective actions. 2. Explain how the recent plant-specific operating experience impacts the Shield Building's ability to perform its intended functions during the period of extended operation. Include a list of any additional aging effects that may require management based on this operating experience. 3. Explain how the recent plant-specific operating experience will be incorporated into the Structures Monitoring Program AMP, and whether the current program will be adequate to manage aging of the shield building
during the period of extended operation, based on this operating experience. Specifically address the following: (a) Details of tests planned to determine the long term effect of the concrete cracks on the ability of the rebars to carry design loads.
Attachment L-12-028 Page 2 of 8 (b) Plans, if any, to repair the crack or reinforce the shield building concrete.(c) Detailed plans to monitor the extent and thickness of cracks, and corrosion of the rebars over the long term. (d) Plans, if any, to perform detailed structural analysis, with explicit modeling of rebars, cracks, and concrete, to demonstrate that the shield building will perform its intended design function over the long term. This analysis should also consider the effect of shrinkage
and environment on the concrete and rebar during the period of
extended operation. 4. Identify and explain any changes to the license renewal application based on the recent plant specific operating experience.
RESPONSE RAI B.2.39-13 1. Summarize the shield building degradation, the root cause, and the expected corrective actions.
Summary of Shield Building Degradation The Shield Building degradation identified using an Impulse Response technique was laminar cracking located within the Shield Building cylinder wall at the outer reinforcing steel (rebar) mat. The crack widths were found to be generally tight, less than or equal to 0.010 inches, with one crack measuring 0.013 inches. The cracking that was first discovered was along the left vertical edge of the temporary construction opening being installed to facilitate the replacement of the reactor pressure vessel head on October 10, 2011. The crack was located
adjacent to the outer rebar mat of the Shield Building cylinder wall in one of the
architectural flute shoulders (architectural shoulders). After the initial investigation determined that this condition was not limited to the area immediately adjacent to this construction opening, an evaluation was performed to investigate other areas of the Shield Building.
The investigation determined that the laminar cracking was evident over an extended portion of the Shield Building structure. The results of this investigation were documented on Attachment #1 (Drawing C-111A) of the Root Cause Report
submitted by FENOC letter dated February 27, 2012 (ML120600056). The Shield Building has sixteen architectural shoulders. Cracking was found (in varying areas)
in each of the fifteen architectural shoulders that were examined; one shoulder was not examined because access was limited due to adjacent equipment. The other areas of cracking were found in portions of the structure that contained a greater amount of rebar. One of the areas was within the top 20 feet of the cylinder wall Attachment L-12-028 Page 3 of 8 that contains #11 horizontal hoop rebar spaced at approximately 6 inches center-to-center. The other area was adjacent to the two main steam line
penetrations in the Shield Building. These areas are located just below the bottoms of shoulders and contain horizontal hoop rebar at approximately 6-inch
center-to-center spacing above the wall penetration.
Summary of the Root Cause Laminar cracking occurred due to the combination of three factors: the design configuration of the architectural shoulders; high moisture intrusion into the Shield
Building concrete followed by a severe temperature drop; and, lack of moisture
prevention on the exterior of the building. The root cause of the Shield Building laminar cracks was attributed to the design specification for construction of the Shield Building, which did not specify the application of an external sealant [for protection] from moisture. The design configuration of the architectural shoulders coupled with a rare combination of severe environmental factors associated with the blizzard of 1978 caused the laminar cracking. The design configuration did not include an external protective sealant on the Shield Building. Lack of an external sealant allowed moisture to be driven into the concrete, freeze, and expand. The
root cause investigation was based on a comprehensive listing of potential failure
scenarios. The Fault Tree (Attachment #11 of the Root Cause Report (ML120600056)) lists 45 potential causes for the cracking. These causes were
evaluated based on plant construction, history (did an event occur?), testing of core bore samples (concrete cores), and analyses.
Concrete core bore samples were taken to confirm suspect locations identified by the Impulse Response testing. These core bore samples were analyzed and material properties were established by tests by several qualified testing facilities.
The test results of the core bore samples taken from the exterior surface of the
Shield Building were used to investigate various fault tree degradation mechanisms
associated with the initial concrete mix design, as-placed concrete, shrinkage, chemical attack, thermal stress cycles, creep, and freeze/thaw damage. The test
results found that the concrete was in good condition, consistent with the mix design, and revealed no abnormal or degraded material properties. The Shield Building was analyzed for a number of actual and postulated events to determine if any of these events could have caused the identified laminar cracks.
The analyses included reviews for thermal effects (extreme heat or cold), wind, tornado, freezing of moisture near the outer rebar mat during blizzard conditions, and excessive density of rebar. Based on the analyses, all potential causes were
eliminated, except for the freezing of moisture during blizzard conditions and excessive density of rebar. Specifically, the investigation reviewed the conditions imposed on this structure by the blizzard of 1978. This storm was unique in that it was preceded by several days of rain and wind. The blizzard conditions arrived on
site with additional moisture, extremely high winds (about 100 miles per hour Attachment L-12-028 Page 4 of 8 maximum), and a rapid temperature drop. The temperature quickly dropped from above freezing to approximately 0 degrees Fahrenheit. The analyses found that
wind-driven moisture penetrated the Shield Building wall and, upon freezing, caused stresses sufficient to cause laminar cracks at the outer rebar mat in the architectural
shoulder regions. This storm was the only event identified that generated sufficient
stress to initiate and propagate the laminar cracking. Additional sensitivity analyses were performed for the areas of dense rebar spacing noted above. This analysis determined that the approximately 6-inch horizontal center-to-center hoop rebar spacing would allow propagation of the laminar cracks in these areas under the conditions previously mentioned. This closer spacing allowed
the concrete to provide less resistance to the propagation of cracks. The same analysis reviewed the typical reinforcement spacing of 12 inches center-to-center in
the remainder of the building and determined that this spacing provided sufficient
concrete between the rebar to preclude laminar cracking. The area of the main steam line penetrations was also reviewed to evaluate the cracking that extends below the auxiliary building roof line into the cylinder walls of
the main steam line rooms at the outer rebar mat. This evaluation concluded that the
cracking extended downward from the bottom of the architectural shoulders just
above the auxiliary building roof line. Higher density rebar of the penetration blockout contributed to crack propagation until equilibrium was reached at the top of
the original wall penetrations. As stated above, the root cause for the laminar cracks has been concluded to be the lack of an exterior sealant to preclude moisture penetration into the Shield Building
wall. The only event that was found to be capable of producing the necessary forces
required to cause the cracks was the 1978 blizzard. The cracking in the architectural
shoulders propagated into some adjacent areas as described above. Summary of the Expected Corrective Actions The expected corrective actions for the Shield Building laminar cracking are summarized as follows: Specify and apply a protective coating or sealant to prevent moisture from penetrating the surface of the Shield Building wall and establish requirements for periodic inspection of the coating or sealant. Develop the necessary documents to provide for the long-term monitoring of the Shield Building laminar cracks (discussed further in response to RAI Request #3 below). Develop the plan and complete the activities for additional investigation of the Shield Building, including any required documentation revisions.
Attachment L-12-028 Page 5 of 8 Develop a plan and finalize the steps to re-establish design and licensing basis conformance for the Shield Building. Initiate additional corrective actions as required. Develop a testing program and complete the activities to determine the structural effect on the steel reinforcement adjacent to the laminar cracks. 2. Explain how the recent plant-specific operating experience impacts the Shield Buildings ability to perform its intended functions during the period of extended operation. Include a list of any additional aging effects that may
require management based on this operating experience.
Based on the investigation conducted in October and November of 2011, and analyses performed to evaluate the as-found conditions, the Shield Building is adequate to perform its intended design functions. As identified in the Root Cause
Report (ML120600056) described above, there are no direct aging effects associated with the identified laminar cracks. The long term monitoring program, described below, is intended to periodically inspect the structure to confirm that there
are no changes in the nature of these cracks. 3. Explain how the recent plant-specific operating experience will be incorporated into the Structures Monitoring Program AMP, and whether the current program will be adequate to manage aging of the shield building during the period of extended operation, based on this operating experience. As noted in the response to RAI Request #2 above, evaluation of the recent Shield Building operating experience did not identify any new aging effects. Therefore, the Structures Monitoring Program will be adequate to manage aging during the period of extended operation. However, a new plant-specific aging management program titled Shield Building Monitoring Program is provided to periodically inspect the structure to confirm that there are no changes in the nature of the identified laminar
cracks. See the response to RAI Request #4 below.
Specifically, address the following:(a) Details of tests planned to determine the long term effect of the concrete cracks on the ability of the rebars to carry design loads.
FENOC plans to administer a testing program to be performed at two independent testing facilities to simulate the as-found cracking in the Shield
Building. The test procedure is planned to test concrete beams to failure. The
concrete beam failures are planned to be strictly controlled such that the laminar cracking would be established in the concrete beams in the area where the
rebar lap splices are planned to be located. By closely monitoring the stresses in the rebar as the test beams undergo failure, the capacity of the rebar at the Attachment L-12-028 Page 6 of 8 splice location can be established. This testing program has a scheduled completion date of August 1, 2012. (b) Plans, if any, to repair the crack or reinforce the shield building concrete. FENOC has no plans at this time to repair the cracks or add reinforcement to the Shield Building concrete. FENOC is developing a comprehensive engineering plan to re-establish the design and licensing basis conformance of
the Shield Building. Development of the plan is scheduled for completion by
December 1, 2012. (c) Detailed plans to monitor the extent and thickness of cracks, and corrosion of the rebars over the long term. Over the long term, a plant-specific Shield Building monitoring aging management program has been developed to perform periodic monitoring of the Shield Building for potential aging effects related to this operating experience.
The Shield Building Monitoring Program also includes inspections or testing to
monitor the condition of the sealant or coating that is planned to be applied to the Shield Building. The requirements of the plant-specific Shield Building
Monitoring Program are to be administered in conjunction with the existing Structures Monitoring Program. See the response to RAI Request #4, below. Also, based on the corrective actions identified in the Shield Building Root Cause Report (ML120600056), the current Davis-Besse procedure for the
evaluation of structures (EN-DP-01511) is being revised to incorporate a section specifically for the long-term monitoring of the Shield Building laminar cracks.
The procedure revision has a scheduled completion date of July 11, 2012. As
described in the corrective actions, current plans are for the procedure to include the following actions to monitor the cracks and ensure the rebar adequacy: Periodic monitoring of the Shield Building is to begin with an annual inspection cycle starting in 2012, with a second inspection in 2013. If the inspection results remain unchanged after the first two inspection cycles (defined as no discernable change in crack width or the
confirmation that no cracks have developed in previously un-cracked core bores), the inspection cycle may be changed to two-years.
Periodic monitoring is to be repeated every two years for a minimum of three cycles. If after those three monitoring cycles, the results of the core bore and crack examinations remain unchanged, the monitoring schedule
may be changed to a five-year cycle.
If any adverse changes are identified (as defined in the acceptance criteria) during these examinations, a condition report would be initiated Attachment L-12-028 Page 7 of 8 to evaluate the changes and to determine the need for revision of the inspection schedule. A minimum of six existing core bores of each type (un-cracked and cracked) are to be inspected during each inspection cycle. The minimum planned distribution of the core bore inspections is as follows: three in
shoulder regions; one in a steam line penetration area; and, two in the
top region of the building outside the shoulders. The examination of the core bores is to be performed by visual inspection and the use of a borescope and optical crack comparator.
Any identified cracks are to be measured using an optical crack
comparator and the borescope. For the examination of the core bores that did not contain a crack indication initially (as defined on Drawing C-111A (ML120600056)), the planned acceptance criterion for cracking is that no new crack indication is identified. If a new crack is identified, it would be measured as described above. Evaluation of the crack would determine the need for
any additional inspections or required changes to the monitoring plans.
Core bores within the sample population that have existing cracks are to be re-examined to determine the current width of the crack. The
as-measured crack width would be compared to the initial crack width measurement as recorded on Drawing C-111A (ML120600056). If it is
determined that the crack width has increased (a discernable change in
width within the accuracy of the measurement technique), the increase
would be evaluated. Chloride ion testing and carbonation testing is to be carried out on a minimum of two new core bore samples collected for examination. This testing is planned to be performed during alternating inspection cycles as detailed in procedural test requirements. The procedural requirements will establish the acceptance criteria for these tests. (d) Plans, if any, to perform detailed structural analysis, with explicit modeling of rebars, cracks, and concrete, to demonstrate that the shield building will perform its intended design function over the long term. This analysis
should also consider the effect of shrinkage and environment on the concrete and rebar during the period of extended operation.
As described above, FENOC is developing a comprehensive engineering plan to re-establish the design and licensing basis conformance of the Shield Building. The plan is scheduled to be completed and issued by December 1, 2012. The plan will include a detailed structural analysis of the Shield Building and consider applicable effects.
Attachment L-12-028 Page 8 of 8 4. Identify and explain any changes to the license renewal application based on the recent plant specific operating experience. The Davis-Besse License Renewal Application is revised as follows: Section 3.5.2.1.1, Containment (including Containment Vessel, Shield Building, and Containment internal structures), is revised to include the Shield Building Monitoring Program under the subheading, Aging
Management Programs. Table 3.5.2-1, Aging Management Review Results - Containment, is revised to include the Shield Building Monitoring Program Existing Section A.1.43, References, is renumbered to A.1.44, References. New Section A.1.43, Shield Building Monitoring Program, is created to include a summary description of a plant-specific Shield Building monitoring aging management program. Monitoring of the Shield Building coating or
sealant is included as a program activity. Appendix A, Updated Safety Analysis Report Supplement, Table of Contents is revised to include Sections A.1.43 and A.1.44. Table A-1, Davis-Besse License Renewal Commitments, is revised to include a license renewal future commitment to implement the Shield Building Monitoring Program prior to entering the period of extended operation. Tables B-1, Correlation of NUREG-1801 and Davis-Besse Aging Management Programs, and B-2, Consistency of Davis-Besse Aging
Management Programs with NUREG-1801, are revised to include the new plant-specific Shield Building Monitoring Program. New Section B.2.43, Shield Building Monitoring Program, is created to include a plant-specific Shield Building monitoring aging management program. Monitoring of the Shield Building coating or sealant is included as a
program activity. Appendix B, Aging Management Programs, Table of Contents is revised to include Section B.2.43. See the Enclosure to this letter for the revision to the DBNPS LRA.
Enclosure Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS)
Letter L-12-028 Amendment No. 25 to theDBNPS License Renewal Application Page 1 of 15 License Renewal Application Sections Affected Section 3.5.2.1.1 Table 3.5.2-1 Table 3.5.2 Plant-Specific Notes Appendix A Table of Contents Section A.1.43
Section A.1.44 Table A-1 Appendix B Table of Contents Table B-1
Table B-2 Section B.2.43 The Enclosure identifies the change to the License Renewal Application (LRA) by Affected LRA Section, LRA Page No., and Affected Paragraph and Sentence. The
count for the affected paragraph, sentence, bullet, etc. starts at the beginning of the affected Section or at the top of the affected page, as appropriate. Below each section the reason for the change is identified, and the sentence affected is printed in italics with deleted text lined-out and added text underlined
.
Enclosure L-12-028 Page 2 of 15 Affected LRA SectionLRA Page No. Affected Paragraph and Sentence3.5.2.1.1Page 3.5-4 New Aging Management Programs bullet In response to request for additional information (RAI) B.2.39-13, a new aging management program bullet is added to the Aging Management Programs subsection of LRA Section 3.5.2.1.1, Containment (including Containment
Vessel, Shield Building, and Containment internal structures), as follows:
Aging Management Programs The following programs are credited for managing the effects of aging on the Containment structural components: 10 CFR Part 50, Appendix J Program Boric Acid Corrosion Program Cranes and Hoists Inspection Program Fire Protection Program Inservice Inspection (ISI) Program - IWE Inservice Inspection (ISI) Program - IWF Shield Building Monitoring Program Structures Monitoring Program Enclosure L-12-028 Page 3 of 15 Affected LRA Section LRA Page No. Affected Paragraph and SentenceTable 3.5.2-1Pages 3.5-72 thru 3.5-74 Rows 77, 78, 79, 80, 82, 83, 84 and 85, Aging Management Program
and Notes columns In response to RAI B.2.39-13, the Aging Management Program and Notes columns for eight rows of LRA Table 3.5.2-1, Aging Management Review Results - Containment, are revised as follows: Table 3.5.2-1 Aging Management Review Results - Containment Row No.Component / Commodity Intended Function 1Material Environment Aging Effect RequiringManagement AgingManagement ProgramNUREG-1801, Volume 2 Item Table 1 Item Notes 77 Shield Building Dome EN, MB, SPB, SRE, SSRConcrete Air-outdoor Loss of MaterialStructures Monitoring 10 CFR Part 50, Appendix J Shield Building Monitoring III.A1-9 3.5.1-23 A 0511 0552 78 Shield Building Dome EN, MB, SPB, SRE, SSRConcrete Air-outdoor Loss of MaterialChange in material properties Structures Monitoring 10 CFR Part 50, Appendix J Shield Building Monitoring III.A1-10 3.5.1-24 A 0511 0552 Enclosure L-12-028 Page 4 of 15 Table 3.5.2-1 Aging Management Review Results - Containment Row No.Component / Commodity Intended Function 1Material Environment Aging Effect RequiringManagement AgingManagement ProgramNUREG-1801, Volume 2 Item Table 1 Item Notes 79 Shield Building Dome EN, MB, SPB, SRE, SSRConcrete Air-outdoor Loss of MaterialCracking Structures Monitoring 10 CFR Part 50, Appendix J Shield Building Monitoring III.A1-6 3.5.1-26 A 0511 0552 80 Shield Building Dome EN, MB, SPB, SRE, SSRConcrete Air-outdoor Change in materialproperties Structures Monitoring 10 CFR Part 50, Appendix J Shield Building Monitoring III.A1-7 3.5.1-32 A 0509 0511 0552 82 Shield BuildingWalls (above grade) EN, FB, MB, SHD, SPB, SRE, SSR Concrete Air-outdoor Loss of MaterialStructures Monitoring 10 CFR Part 50, Appendix J Fire Protection
Shield Building Monitoring III.A1-9 3.5.1-23 A 0511 0512 0552 83 Shield BuildingWalls (above grade) EN, FB, MB, SHD, SPB, SRE, SSR Concrete Air-outdoor Loss of MaterialChange in material properties Structures Monitoring 10 CFR Part 50, Appendix J Fire Protection Shield Building Monitoring III.A1-10 3.5.1-24 A 0511 0512 0552 Enclosure L-12-028 Page 5 of 15 Table 3.5.2-1 Aging Management Review Results - Containment Row No.Component / Commodity Intended Function 1Material Environment Aging Effect RequiringManagement AgingManagement ProgramNUREG-1801, Volume 2 Item Table 1 Item Notes 84 Shield BuildingWalls (above grade) EN, FB, MB, SHB, SPB, SRE, SSR Concrete Air-outdoor Loss of MaterialCracking Structures Monitoring 10 CFR Part 50, Appendix J Fire Protection Shield Building Monitoring III.A1-6 3.5.1-26 A 0544 0552 85 Shield Building Walls (above grade) EN, FB, MB, SHD, SPB, SRE, SSR Concrete Air-outdoor Change in material properties Structures Monitoring 10 CFR Part 50, Appendix J Fire Protection Shield BuildingMonitoring III.A1-7 3.5.1-32 A 0509 0511 0512 0552 Enclosure L-12-028 Page 6 of 15 Affected LRA SectionLRA Page No. Affected Paragraph and Sentence Table 3.5.2 Plant-Specific NotesPage 3.5-172 New Note / Row In response to RAI B.2.39-13, LRA Table 3.5.2 Plant-Specific Notes is revised to add a new plant-specific note as follows: Plant-Specific Notes:
0552 In addition to aging management by the Structures Monitoring Program, the Shield Building concrete walls that are exposed to air-outdoor are also managed by the plant-specific Shield Building Monitoring Program. For the Shield Building dome, in additio n to the Structures Monitoring Program,the plant-specific Shield Building Monitoring Program will be used to manage only the coating or sealant applied to the dome.
Enclosure L-12-028 Page 7 of 15 Affected LRA Section LRA Page No. Affected Paragraph and SentenceA.1.43 & A.1.44Page A-25 New Section / Title Revision Appendix A Table of ContentsPage A-4 A.1.43 & A.1.44 In response to RAI B.2.39-13, a new LRA section is created to include a new plant-specific aging management program. LRA Section A.1.43 is renamed from References to Shield Building Monitoring Program. The References section
is renumbered as Section A.1.44, References. Although not shown below, LRA Appendix A, Updated Safety Analysis Report Supplement, Table of Contents on LRA Page A-4, is revised accordingly to include the renumbered sections.
New LRA Section A.1.43 reads as follows: A.1.43 Shield Building Monitoring ProgramThe Shield Building Monitoring Program is a prevention and condition monitoring program. The program consists of inspections, testing or chemical analyses of the Shield Building concrete and reinforcing steel (rebar). The inspections, testing or chemical analyses conducted as part of the Shield Building Monitoring Program supplement the inspections conducted as part of the Structures Monitoring Program.The program monitors for cracking, change of material properties and loss of material of concrete. The program also will monitor for corrosion of the concrete rebar. As a preventive action of this program, the Shield Building exterior concrete sealant or coating is inspected or tested for evidence of loss of its effectiveness.
Visual inspections are performed on rebar (when exposed), core bore and core bore sample (concrete core) surfaces using plant-specific procedures implemented by inspectors qualified through plant-specific procedures.The Shield Building Monitoring Program includes periodic scheduled inspections, testing or chemical analyses to ensure that the existing environmental conditions are not causing material degradation that could result in loss of Shield Building intended functions during the period of extended operation.Implementation of this program ensures that the intended functions of the Shield Building are maintained during the period of extended operation.
Enclosure L-12-028 Page 8 of 15 Affected LRA SectionLRA Page No. Affected Paragraph and SentenceTable A-1Page A-69 Commitment No. 46 In response to RAI B.2.39-13, LRA Table A-1, Davis-Besse License Renewal Commitments, license renewal future Commitment No. 46, previously identified as not used in FENOC letter dated October 7, 2011 (ML11285A064), is replaced in its entirety to read as follows:
Table A-1 Davis-Besse License Renewal Commitments Item Number Commitment Implementation Schedule Source Related LRA Section No./
Comments 46 Not used.Implement the Shield Building Monitoring Program as described in LRA Section B.2.43.
Prior toApril 22, 2017 LRA and FENOC Letter L-12-028 A.1.43 B.2.43Response to NRC RAI B.2.39-13from NRC Letter datedDecember 27, 2011 Enclosure L-12-028 Page 9 of 15 Affected LRA Section LRA Page No. Affected Paragraph and SentenceTable B-1 Page B-17 New Row In response to RAI B.2.39-13, a new plant-specific program row is added to Table B-1, Correlation of NUREG-1801 and Davis-Besse Aging Management
Programs , for the new Shield Building Monitoring Program, as follows:
Table B-1 Correlation of NUREG-1801 and Davis-Besse Aging Management Programs (continued)Number NUREG-1801 Program Corresponding Davis-Besse AMP NA Plant-specific Program Shield Building Monitoring Program.
See Section B.2.43.
Affected LRA Section LRA Page No. Affected Paragraph and SentenceTable B-2 Page B-22 New Row In response to RAI B.2.39-13, a new row is added to Table B-2, Consistency of Davis-Besse Aging Management Programs with NUREG-1801, for the new plant-specific Shield Building Monitoring Program, as follows:
Program NameNew / Existing Consistentwith NUREG-1801 Consistentwith NUREG-1801 with Exceptions Plant-Specific Enhancement Required Shield Building Monitoring Program Section B.2.43 New----Yes--
Enclosure L-12-028 Page 10 of 15 Affected LRA Section LRA Page No. Affected Paragraph and SentenceB.2.43Page B-166 Entire Section In response to RAI B.2.39-13, new LRA Section B.2.43, Shield Building Monitoring Program, is created to include a new plant-specific aging
management program. Although not shown below, LRA Appendix B, Aging
Management Programs, Table of Contents on LRA Page B-4, is revised accordingly to include the new section. New LRA Section B.2.43 reads as follows:
B.2.43 SHIELD B UILDING MONITORING PROGRAM Program DescriptionThe Shield Building Monitoring Program is a new plant-specific prevention and condition monitoring program for Davis-Besse. The program will consist of inspections, testing or chemical analyses of the Shield Building concrete and reinforcing steel (rebar). The inspections, testing or chemical analyses conducted as part of the Shield Building Monitoring Program will supplement the inspections conducted as part of the Structures Monitoring Program.The program will monitor for cracking, change of material properties and loss of material of concrete. The program also will monitor for corrosion of the concrete rebar. As a preventive action of this program, the Shield Building exteriorconcrete sealant or coating will be inspected or tested for evidence of loss of its effectiveness.
Visual inspections will be performed on rebar (when exposed), core bore and core bore sample (concrete core) surfaces using plant-specific procedures implemented by inspectors qualified through plant-specific procedures.
The Shield Building Monitoring Program will include periodic scheduled inspections, testing or chemical analyses to ensure that the existing environmental conditions are not causing material degradation that could result in loss of Shield Building intended functions during the period of extended operation.Implementation of this program will ensure that the intended functions of the Shield Building are maintained during the period of extended operation.
Enclosure L-12-028 Page 11 of 15 NUREG-1801 ConsistencyThe Shield Building Monitoring Program is a new plant-specific Davis-Besse program for license renewal. While NUREG-1801 includes a Structures Monitoring Program (XI.S6), the Davis-Besse Shield Building Monitoring Program is considered plant-specific, and is evaluated against the ten elements described in Appendix A of the Standard Review Plan of License Renewal Applications for Nuclear Power Plants, NUREG-1800.Aging Management Program ElementsThe results of an evaluation of each program element are provided below.ScopeThe scope of the Shield Building Monitoring Program includes the Shield Building reinforced concrete and rebar.The program will include periodic inspections, testing or chemical analyses to ensure that the existing environmental conditions are not causing material degradation that could result in a loss of any of the intended functions of the Shield Building during the period of extended operation.Preventive ActionsAs part of the Shield Building Monitoring Program, the Shield Building sealant or coating will be inspected or tested to verify its continuing effectiveness during the period of extended operation.Parameters Monitored or InspectedThe Shield Building Monitoring Program will inspect parameters directly related to potential degradation of the components under review, including visual evidence of cracking, change of material properties, loss of material and corrosion. Also, since visual inspection may not detect change of material properties prior to a loss of function, chemical analyses of concrete will be used, as applicable. In addition, the Shield Building exterior concrete sealant or coating will be inspected or tested for loss of its effectiveness.The parameters to be inspected will include visual evidence of surface degradation, such as cracking, change in material properties, loss of material and corrosion. Chemical analyses may be used, as needed, to determine chloride content and carbonation of concrete. Observed conditions, testing results or chemical analyses results may indicate a need to conduct Enclosure L-12-028 Page 12 of 15 augmented inspections, testing or analyses. American Concrete Institute (ACI) Report 349.3R, Evaluation of Existing Nuclear Safety-Related Concrete Structures, and ANSI/ASCE 11-90, Guideline for Structural Condition Assessments of Existing Buildings, provide guidance for the selection of parameters to be monitored or inspected.Parameters Monitored or Inspected and Potential Aging Effects Potential Aging Effect Potential Aging Mechanisms ParametersMonitoredInspection and TestingMethod(s)Cracking (concrete)Freezing of water that has permeated the concreteSurface condition of core bores and core bore samples, and change in crack conditions VisualChange of Material PropertiesLeaching of calcium hydroxide from concreteSurface condition of core bores and core bore samples Visual Loss of Material (concrete)Freezing of water that has permeated the concreteSurface condition of core bores and core bore samples Visual Loss of Material (rebar)CorrosionChlorides in concrete and carbonation of concreteChemical analysis,as needed Loss of Material (rebar)CorrosionSurface condition of rebar, when exposed Visual Loss ofSealant or Coating Effectiveness Loss of ability to perform itsprotective action Condition of thesealant or coating[To be developed once the coating or sealant is selected and applied]Detection of Aging EffectsThe Shield Building Monitoring Program provides for detection of aging effects prior to the loss of Shield Building intended functions. The inspections, testing and analyses of the Shield Building concrete and rebar that was done to support the root cause evaluation will provide a baseline for future Shield Building Monitoring Program activities.Periodic visual inspections, testing and chemical analyses will be performed using plant-specific procedures implemented by inspectors qualified through plant-specific procedures.
Enclosure L-12-028 Page 13 of 15 Visual inspections will be supplemented by other established nondestructive examination (NDE) techniques and testing, as appropriate.The initial frequency of visual inspection of core bores and core bore samples will be based on the results of inspections conducted before the period of extended operation. If no aging effects were identified by these visualinspections, then visual inspections will continue to be conducted at least once every two years during the period of extended operation. If no aging effects are identified by the two-year interval visual inspections (defined as no discernable change in crack width or the confirmation that no visible cracks have developed in core bores that previously had no visible cracks), then the frequency of visual inspections may be changed to at least once every five years. The initial frequency of chloride ion testing and carbonation testing of concrete will be based on the results of chloride ion testing and carbonation testing conducted before the period of extended operation. Any evidence of degradation will be documented and evaluated through the FENOC Corrective Action Program. The evaluation will include a determination of the need for any required change to the inspection schedule. The inspection or testing method and frequency of the Shield Building exterior concrete sealant or coating will be established prior to entering the period of extended operation. The frequency of the sealant or coating inspection ortesting may be adjusted based on observed sealant or coating conditions, any required reapplication of the sealant or coating, or on the recommendations of the sealant or coating manufacturer.Monitoring and TrendingThe Shield Building Monitoring Program will include a baseline inspection, followed by periodic inspections, testing or chemical analyses. Visual inspections, testing or chemical analyses will be performed by qualified personnel, as defined by plant-specific procedures. Inspection, testing and analytic findings will be documented and evaluated by assigned engineering personnel such that the results can be trended. Inspection findings that do not meet acceptance criteria will be evaluated and tracked using the FENOC Corrective Action Program.Acceptance CriteriaIndications of relevant conditions of degradation detected during the inspections, tests or analyses will be evaluated and compared to pre-determined acceptance criteria. The acceptance criteria will be defined to ensure that the need for corrective actions is identified before loss of structure or component intended functions. If the acceptance criteria are not met, then Enclosure L-12-028 Page 14 of 15 the indications or conditions will be evaluated under the FENOC Corrective Action Program.Engineering evaluation by qualified personnel will be used for disposition of inspection findings, test results or analytic results that do not meet the acceptance criteria. Unacceptable inspection findings will include evidence of new cracking, growth of previously identified cracks, loss of material, change of material properties and corrosion that could lead to loss of a Shield Building intended function during the period of extended operation. Evidence of new cracking is defined as a visual inspection finding that visible cracks have developed in core bores that previously had no visible cracks. Growth of previously identified cracks is defined as a visual inspection finding that there has been a discernable change in crack width.The acceptance criteria for the sealant or coating will be based on the ability of the sealant or coating to continue to be effective.Corrective ActionsThis element is common to Davis-Besse programs and activities that are credited with aging management during the period of extended operation and is discussed in Section B.1.3.Confirmation ProcessThis element is common to Davis-Besse programs and activities that are credited with aging management during the period of extended operation and is discussed in Section B.1.3.Administrative ControlsThis element is common to Davis-Besse programs and activities that are credited with aging management during the period of extended operation and is discussed in Section B.1.3.Operating ExperienceReview of Davis-Besse operating experience identified degradation of the Shield Building concrete wall (above grade) due to internal laminar cracking. The degradation had not been identified by the existing Structures Monitoring Program, which is based on visual inspection of the external surfaces of structures. Although the laminar cracking degradation of the concrete for the Shield Building was not caused by an aging mechanism, it is prudent to establish a plant-specific Aging Management Program to include monitoring Enclosure L-12-028 Page 15 of 15 methods to identify aging effects that may occur in the future. The Shield Building Monitoring Program is designed to identify and evaluate potential aging effects within the Shield Building walls. The program is also designed to identify and evaluate any loss of preventive action effectiveness of the exterior Shield Building concrete sealant or coating, once it has been selected and applied.Industry operating experience regarding similar structures was evaluated for applicability at Davis-Besse. The only other similar instance of concrete delamination discovery associated with creating a temporary access opening in the containment structure occurred at Crystal River Unit 3. The root cause of the Crystal River containment concrete delamination was the design of the structure in combination with the type of concrete used, and the acts of detensioning and opening the containment structure. As part of the root cause analysis of the Davis-Besse Shield Building laminar cracking, FENOC concluded that the subject Crystal River operating experience was not applicable to the Davis-Besse Shield Building.The elements that comprise the Shield Building Monitoring Program inspections, testing or analyses will be consistent with industry practice. Industry and plant-specific operating experience will be considered in the implementation of this program. As additional operating experience is obtained, lessons learned will be incorporated, as appropriate.
Enhancements None.ConclusionImplementation of the Shield Building Monitoring Program will provide reasonable assurance that the existing environmental conditions will not cause aging effects that could result in a loss of component intended function. Aging effects that are discovered will be managed such that the component intended functions will be maintained consistent with the current licensing basis during the period of extended operation.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD
)
In the Matter of )
) Docket No. 50-346-LR FIRSTENERGY NUCLEAR OPERATING COMPANY )
)
(Davis-Besse Nuclear Power Station, Unit 1) ) April 5, 2012
) CERTIFICATE OF SERVICE I hereby certify that, on this date, a copy of the Notification of Filing Related to Proposed Shield Building Cracking Contention was filed with the Electronic Information Exchange in the above-captioned proceeding on the following recipients.
Administrative Judge William J. Froehlich, Chair Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001 E-mail: wjf1@nrc.gov
Administrative Judge Dr. William E. Kastenberg Atomic Safety and Licensing Board Panel
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001 E-mail: wek1@nrc.gov
Office of the Secretary
U.S. Nuclear Regulatory Commission Rulemakings and Adjudications Staff
Washington, DC 20555-0001 E-mail: hearingdocket@nrc.gov
Administrative Judge Nicholas G. Trikouros Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001 E-mail: nicholas.trikouros@nrc.gov
Office of the General Counsel
U.S. Nuclear Regulatory Commission
Mail Stop O-15D21
Washington, DC 20555-0001
Brian G. Harris Megan Wright Emily L. Monteith Catherine E. Kanatas E-mail: Brian.Harris@nrc.gov; Megan.Wright@nrc.gov; Emily.Monteith@nrc.gov;
Catherine.Kanatas@nrc.gov
2DB1/ 69460150.1
Office of Commission Appellate Adjudication
U.S. Nuclear Regulatory Commission
Mail Stop: O-16C1
Washington, DC 20555-0001 E-mail: ocaamail@nrc.gov
Kevin Kamps
Paul Gunter
6930 Carroll Avenue, Suite 400 Takoma Park, MD 20912 E-mail: kevin@beyondnuclear.org;
paul@beyondnuclear.org
Michael Keegan Dont Waste Michigan
811 Harrison Street
Monroe, MI 48161 E-mail: mkeeganj@comcast.net
Terry J. Lodge
316 N. Michigan St., Ste. 520
Toledo, OH 43604 E-mail: tjlodge50@yahoo.com Signed (electronically) by Jane T. Accomando Jane T. Accomando Morgan, Lewis & Bockius LLP 1111 Pennsylvania Avenue, N.W.
Washington, DC 20004
Phone: 202-739-5815 E-mail: jaccomando@morganlewis.com Counsel for FENOC