Text

Response to NRC Request for Additional Information for the Review of License Renewal Application - Set 8
	ML14363A092
Person / Time
Site:	Fermi
Issue date:	12/26/2014
From:	Philippon M; DTE Electric Company
To:	; Document Control Desk, Division of License Renewal
References
	NRC-14-0082
	Download: ML14363A092 (39)
	v • d • e

Vito A. Kaminskas Site Vice President DTE Energy Company 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.6515 Fax: 734.586.4172 Email: kaminskasv@dteenergy.com DTE Energy-10 CFR 54 December 26, 2014 NRC-14-0082 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001

References:

1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

2) DTE Electric Company Letter to NRC, "Fermi 2 License Renewal Application," NRC-14-0028, dated April 24, 2014 (ML14121A554)

3) NRC Letter, "Requests for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 8 (TAC No.

MF4222)," dated November 25, 2014 (ML14322A526)

Subject:

Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 8 In Reference 2, DTE Electric Company (DTE) submitted the License Renewal Application (LRA) for Fermi 2. In Reference 3, NRC staff requested additional information regarding the Fermi 2 LRA. The Enclosure to this letter provides the DTE response to the request for additional information.

One new commitment is being made in this submittal to revise plant procedures to include acceptance criteria for masonry wall inspections that ensure observed aging effects do not invalidate the wall's evaluation basis or impact its intended function.

This commitment is added to the LRA as Item 34.1 in Table A.4 as indicated in the response to RAI B.1.25-1.

In addition, a clarification has been made to commitments previously identified in the LRA to specifically indicate the use of the 2002 or later version for Structures Monitoring Program enhancements that reference ACI 349.3R. These revised commitments are in Item 34 in Table A.4 as indicated in the response to RAI B.1.42-3.

USNRC NRC-14-0082 Page 2 Should you have any questions or require additional information, please contact Lynne Goodman at 734-586-1205.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on December 26, 2014 Michel A. Philippon Director Nuclear Production (Plant Manager)

For Vito A. Kaminskas

Enclosure:

DTE Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 8 cc: NRC Project Manager NRC License Renewal Project Manager NRC Resident Office Reactor Projects Chief, Branch 5, Region III Regional Administrator, Region III Michigan Public Service Commission, Regulated Energy Division (kindschl@michigan.gov)

Enclosure to NRC-14-0082 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 DTE Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 8

Enclosure to NRC-14-0082 Page 1 RAI B.JL25-1

Background

Title 10 of the Code of FederalRegulations (10 CFR) Section 54.21(a)(3) requires applicants to demonstrate that the effects of aging will be adequately managed so that intendedfunctions will be maintainedconsistent with the currentlicensing basis (CLB) during the period of extended operation.

License Renewal Application (LRA) Section B.1.25 states that the Masonry Wall Programis consistent, with enhancements, with GALL Report AMP XL S5, "Masonry Walls." The "acceptance criteria"program element of GALL ReportAMP XL S5 states that "foreach masonry wall, the extent of observed shrinkage and/orseparationand cracking of masonry may not invalidate the evaluation basis or impact the wall's intendedfunction." However, during the audit, the staff noted that the "acceptancecriteria"program element of the LRA aging managementprogram (AMP) basis document for the Masonry Wall Programstates that potential non-conforming conditions identified during the course of an inspection are noted, evaluated,and corrective action taken as necessary. The staff also noted that in Section 4 of the referencedMMR14 procedure, the qualitative criteriafor evaluation of inspection results are describedin terms of structuralfunction only.

Issue It is not clear that the "acceptance criteria"program element of LRA Section B.1.25, "Masonry Wall," is consistent with the recommendations in GALL ReportAMP XI S5 because this program element does not appear to address the "invalidate evaluation basis" aspect of the acceptance criteria.

Request

1. Clarify how the acceptance criteriafor the inspection of masonry walls are consistent with that describedin GALL ReportAMP XLS5. If it is determined that a program enhancement is neededfor consistency with GALL Report AMP XI S5, provide the supportingprogram enhancement.

2. If criteriaother than that describedin the GALL Report are being used,provide a descriptionof the exception that includes the acceptance criteriaand technical basisfor its determination.

Response

1. The Fermi 2 program procedure for masonry walls includes acceptance criteria that ensure observed conditions do not impact the wall's capability to perform its structural functions.

This ensures the observed conditions do not invalidate the wall's evaluation basis or impact

Enclosure to NRC-14-0082 Page 2 its intended function. To clarify that the acceptance criteria for the inspection of masonry walls are consistent with those described in NUREG-1801 Generic Aging Lessons Learned (GALL) Report AMP XI.S5, the "acceptance criteria" for the program described in License Renewal Application (LRA) Section B.1.25, "Masonry Wall," will be revised to address the "invalidate evaluation basis" aspect. This enhancement to the Masonry Wall Program (LRA Sections A.1.25 and B.1.25) is added to the enhancements to the Structures Monitoring Program (LRA Sections A.1.42 and B.1.42). The revisions to the LRA are indicated below.

2. The acceptance criteria, with enhancements, as described in the GALL Report were used.

LRA Revisions:

LRA Sections A.1.42, A.4, and B.1.42 are revised as shown on the following pages. Additions are shown in underline and deletions are shown in strike-through.

Enclosure to NRC-14-0082 Page 3 A.1.42 Structures Monitoring Program Revise plant procedures to prescribe quantitative acceptance criteria based on the quantitative acceptance criteria of ACI 349.3R and information provided in industry codes, standards, and guidelines including ACI 318, ANSI/ASCE 11, and relevant AISC specifications. Industry and plant-specific operating experience will also be considered in the development of the acceptance criteria.

" Revise plant procedures to include accetance criteria for masonry wall inspections that ensure observed aging effects (cracking loss of material or gaps between the structural steel supports and masony wails) do not invalidate the wall's evaluation basis or impact its intended function.

Enclosure to NRC-14-0082 Page 4 A.4 LICENSE RENEWAL COMMITMENT LIST Implementation No. Program or Activity Commitment Schedule Source 34 Structures Monitoring Enhance Structures Monitoring Program as follows: Prior to September A.1.42 20, 2024

k. Revise plant procedures to prescribe quantitative acceptance criteria based on the quantitative acceptance criteria of ACI 349.3R and information provided in industry codes, standards, and guidelines including ACI 318, ANSI/ASCE 11, and relevant AISC specifications. Industry and plant-specific operating experience will also be considered in the development of the acceptance criteria.

I. Revise plant procedures to ncudeaccetancecriteria for masonr wall inspections that ensure observed ang effects crackin loss of material or as between the structural steel suports and masonry_walls do notinvalidate the wall's evaluation basis or im act its intended function.

Enclosure to NRC-14-0082 Page 5 B.1.42 STRUCTURES MONITORING Element Affected Enhancement

6. Acceptance Criteria Revise plant procedures to prescribe quantitative acceptance criteria based on the quantitative acceptance criteria of ACI 349.3R and information provided in industry codes, standards, and guidelines including ACI 318, ANSI/ASCE 11 and relevant AISC specifications. Industry and plant-specific operating experience will also be considered in the development of the acceptance criteria.

Revise plant procedures to include acceptance criteria for masonry wall inspections that ensure observed aging effects (cracking, loss of material or gaps between the structural steel arts and masonry walls) do not invalidate the wall's evaluation basis or impact its intended function.

Enclosure to NRC-14-0082 Page 6 RAI B.1.39-1

Background:

Section 54.21(a)(3) of 10 CFR requires the applicantto demonstrate that the effects of agingfor structures and components will be adequately managedso that the intendedfunction(s) will be maintainedconsistent with the CLB for the period of extended operation. As describedin SRP-LR, an applicantmay demonstrate compliance with 10 CFR 54.21(a)(3) by referencing the GALL Report and when evaluation of the matter in the GALL Report applies to the plant.

LRA Section B.1.39, "RG 1.127, Inspection of Water-ControlStructuresAssociated with Nuclear Power Plants," which is implemented as part of LRA Section B.1.42, "StructuresMonitoring,"

states that the program is an existing program that,following enhancement, will be consistent with GALL Report AMP X S7. The "detection of aging effects" program element of GALL Report AMP XJ.S7 states that the program should include provisionsfor increasedinspection frequency if the extent of the degradationis such that the structure or component may not meet its design basis if allowed to continue uncorrecteduntil the next normally scheduled inspection.

However, during the AMP audit, the staff noted that the applicant'sAMP does not address the provisionsfor morefrequent inspections.

Issue:

It is not clear that the "detection of aging effects "program element of the Regulatory Guide (RG) 1.127, Inspection of Water-ControlStructures Associated with Nuclear Power Plants Programis consistent with the recommendations in GALL Report AMP X. S7 regarding provisionsfor morefrequent inspections.

Request:

1. State how the LRA RG 1.127, Inspection of Water-ControlStructures Associated with Nuclear Power PlantsProgram is consistentwith the GALL Reportprovisionfor identifying and addressingthe need to increase inspectionfrequency to adequately manage the effects of aging, during the period of extended operation.

2. Otherwise, provide the technicaljustificationfor the exception to the GALL Report recommendation.

Response

Fermi 2 License Renewal Application (LRA) Section B.1.39, Inspection of Water-Control Structures Associated with Nuclear Power Plants, states that the program is one that requires periodic monitoring and maintenance of water-control structures so that the consequences of age-related deterioration and degradation can be prevented or mitigated in a timely manner. The program is implemented as part of the Structures Monitoring Program (LRA Section B.1.42).

Enclosure to NRC-14-0082 Page 7 As is stated in LRA Section B.1.42 "Program Description" for Structures Monitoring, inspections are performed at a frequency sufficient to ensure there is no loss of intended function between inspections, and the program will be enhanced to perform inspections at least once every five years. Also as is stated in LRA Section B.1.42, the program already contains provisions for increased inspection frequency and trending of structures and components in accordance with 10 CFR 50.65(a)(1), if the extent of degradation is such that the structure or component may not meet its design basis or, if degradation is allowed to continue uncorrected until the next normally scheduled assessment, the structure may not meet its design basis. This existing provision for increased inspection frequency and trending of structures and components is consistent with the NUREG-1801 Generic Aging Lessons Learned (GALL) Report recommendations for identifying and addressing the need to increase inspection frequency to adequately manage the effects of aging during the period of extended operation. Because this is a provision in the existing Structures Monitoring Program, an additional enhancement was not added to the "detection of aging effects" element in either LRA Section B.1.42 or B.1.39.

LRA Revisions:

None.

Enclosure to NRC-14-0082 Page 8 RAI B.1.39-2 Backround:

LRA Section B.1.39 states that the RG 1.127, Inspection of Water-ControlStructuresAssociated with Nuclear Power Plants Program "performsperiodicvisual examinations to monitor the water-controlstructures and structuralcomponents, including...steel piles requiredfor the stability of the shore barrier." LRA Table 3.5.2-2, "Water-ControlStructures Summary of Aging Management Evaluation," indicates that the Structures MonitoringProgramwill manage the carbon steel sheet pilesfor the shore barrier,exposed to air - outdoor or a fluid environment,for loss of material. However, during its onsite audit, thru discussion with the applicant,the staff became aware that the applicantdoes not plan to perform visual inspections of the submerged steel piles at the shore barrieras described in LRA Section B.1.39.

Issue:

For these components identified in the LRA as within the scope of license renewal and subject to an AMR, it is not clear how either the RG 1.127, Inspection of Water-ControlStructures Associated with Nuclear Power Plants Programor the Structures Monitoring Programwill manage loss of materialof the "steelpiles requiredfor stability of the shore barrier"ifvisual inspection will not be performed Request:

Clarify whether the steelpiles at the shore barrierwill be managedfor age-relateddegradation thru visual inspections as described in the LRA, and if not, describe how the proposedAMP(s) will adequately manage the effects of aging during the period of extended operation.

Response

When following the Fermi 2 site surveillance procedure for the shore barrier, if deviations greater than the acceptance criteria given in the procedure are noted during the inspection of the overall shore barrier, a corrective action document is generated and an evaluation of the overall acceptability and functionality of the entire shore barrier structure is performed. Additionally, the site surveillance procedure for the shore barrier requires that steel sheet pile component alignment is visually checked while perfonning the surveillance if the lake level permits.

The steel sheet pile component of the shore barrier was conservatively included in the License Renewal Application (LRA) as in-scope and subject to aging management review (AMR).

However, based on further evaluation and from evidence presented below, the steel sheet pile component of the Fenni 2 shore barrier does not perform a license renewal intended function.

The Fermi 2 Updated Final Safety Analysis Report (UFSAR) Figure 2.4-22 showing the shore barrier configuration in combination with the shore barrier construction specification referenced

Enclosure to NRC-14-0082 Page 9 in UFSAR Figure 2.4-22 indicate that the stone and fill component of the barrier was installed as a Quality Assurance (QA) Level I safety-related structure while the steel sheet pile was procured and installed as a QA Level III (non-Q) component. The shore barrier drawing also shows that the top of the sheet piling was cut to an elevation of 572'-0" after armor stone placement. This cut elevation is lower than the expected normal mean monthly lake level of 574.4' that is specified on the drawing. The shore barrier construction specification referenced in the UFSAR figure also specifies that the steel sheet piling was installed solely to facilitate shore barrier construction activities. The fact that the steel sheet piling was installed as a QA Level III component while the rest of the shore barrier is designated as QA Level I and the fact that the shore barrier construction specification states that the sheet piling was installed solely to facilitate shore barrier construction activities demonstrates that the steel sheet pile is not credited as a structural support for the safety-related shore barrier stones and was only used as a construction aid. The fact that the sheet piling was cut off at an elevation that is below the normal lake water level also shows that the sheet piling was not credited as part of the flood barrier feature.

Fermi 2 LRA Sections A.1.39 and B.1.39 state that the steel sheet piles are required for the stability of the shore barrier. LRA Table 2.4-2 related to scoping and screening methodology for identifying structures and components subject to AMR states that the two intended functions of the steel sheet piles for the shore barrier are "Flood Barrier" and "Support for Criterion (a)(1) equipment." From the evidence presented in the above discussion, the steel sheet piles do not in fact perform either of these two specified intended functions. Therefore, the steel sheet pile component of the shore barrier is not within the scope of license renewal. The LRA will be revised as indicated below.

LRA Revisions:

LRA Tables 2.4-2, 3.5.1 (item 3.5.1-79), and 3.5.2-2 (and associated plant-specific note 502) and LRA Sections A.1.39 and B.1.39 are revised as shown on the following pages. Additions are shown in underline and deletions are shown in strike-through.

Enclosure to NRC-14-0082 Page 10 Table 2.4-2 Water-Control Structures Components Subject to Aging Management Review Component Intended Functiona Steel and Other Metals Fire protection fuel-oil storage tank support Support for Criterion (a)(3) equipment Steel components: beams, columns, plates Enclosure, protection Heat sink Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Steel components: monorails Support for Criterion (a)(2) equipment Steel chet piles for chure berrier ozSupor Floeed-baFYef for Criterion (a)(-1) equipment~

Enclosure to NRC-14-0082 Page 11 Table 3.5.1 Structures and Component Supports Aging Item Aging Effect/ Management Further Evaluation Number Component Mechanism Programs Recommended Discussion 3.5.1-78 Steel Cracking due to Water Chemistry No, unless leakages Consistent with NUREG-components: stress corrosion and Monitoring of have been detected 1801. The Water fuel pool liner cracking; Loss of the spent fuel pool through the SFP liner Chemistry Control - BWR material due to water level in that cannot be Program and monitoring of pitting and crevice accordance with accounted for from the the spent fuel pool water corrosion technical leak chase channels level in accordance with specifications and technical specifications leakage from the and leakage from the leak leak chase chase channels manages channels. the listed aging effects.

3.5.1-79 Steel Loss of material Structures No Consstent-with4 R-G components: due to corrosion Monitoring Program 4894-The-Strueur-e piles Moiengran annage~h~esat effeetThe steel piles at Fermi 2 do not perorm a license renewal intended function and therefore do not re quire an aginig management rogram.

3.5.1-80 Structural bolting Loss of material Structures No Consistent with NUREG-due to general, Monitoring Program 1801. The Structures pitting and crevice Monitoring Program corrosion manages the listed aging effect.

Enclosure to NRC-14-0082 Page 12 Notes for Table 3.5.2-1 through 3.5.2-4 Generic Notes A. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description.

B. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP takes some exceptions to NUREG-1801 AMP description.

C. Component is different, but consistent with material, environment, aging effect, and aging management program for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description.

D. Component is different, but consistent with material, environment, aging effect, and aging management program for NUREG-1801 line item. AMP takes some exceptions to NUREG-1801 AMP description.

E. Consistent with NUREG-1801 material, environment, and aging effect but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program.

F. Material not in NUREG-1801 for this component.

G. Environment not in NUREG-1801 for this component and material.

H. Aging effect not in NUREG-1801 for this component, material and environment combination.

I. Aging effect in NUREG-1801 for this component, material and environment combination is not applicable.

J. Neither the component nor the material and environment combination is evaluated in NUREG-1801.

Plant-Specific Notes 501. The drywell support skirt is embedded in the concrete of the reactor pedestal and is similar to concrete reinforcing environment. Therefore, this component aging is addressed by the surrounding concrete aging management program.

502. Because steeie stel piles drien into disqturbcd soils have expcrienc-ed only mIinor to moderatc corrosio fefewal term, no- aging mna-Rgement is required.

Enclosure to NRC-14-0082 Page 13 Table 3.5.2-2 Water-Control Structures Summary of Aging Management Review Table 3.5.2-2: Water-Control Structures Structure and/or Aging Effect Aging Component or Intended Requiring Management NUREG- Table 1 Commodity Function Material Environment Management Programs 1801 Item Item Notes Steel SNS Carbon Air- indoor Loss of material RG 1.127 IIl.A6.TP- 3.5.1-83 C components: steel uncontrolled 221 monorails Steek-eheet FLBSSR Cartefm Air-eutdeer Lossfmateral StFetWes 44A3TP 3.-5-7-7 A pilee-f-ersheFe steel Mentering g2 barfieF Stee"sheet Ft -SSR Garben Exposed-t Less-ofmatcral Stautuwes U4A3-T-- 3-5-1-7-9 A pile 4er-shore steel fluid Monitnr4Ag 249 barfier enverarent Steel-eheet FLBrSSR Gadren So# None None 4 502 piles f erShere steel Beams, EN, FLB, Concrete Air - indoor Cracking, loss of RG 1.127 Ill.A6.TP- 3.5.1-59 A columns and HS, MB, uncontrolled bond, and loss 38 floor slabs SNS, of material SRE, SSR (spalling, scalina)

Enclosure to NRC-14-0082 Page 14 A.1.39 RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants Program Fermi 2 is not committed to the requirements of NRC Regulatory Guide (RG) 1.127, "Inspection of Water-Control Structures Associated with Nuclear Power Plants." However, the program at Fermi 2 was developed based on guidance provided in the NRC RG 1.127, Revision 1, and provides an inservice inspection and surveillance program for the Fermi 2 shore barrier and raw water-control structures associated with emergency cooling water systems or flood protection.

The scope of the Fermi 2 program includes water-control structures within the scope of license renewal as delineated in 10 CFR 54.4. The program performs periodic visual examinations to monitor the condition of water-control structures and structural components, including structural steel and structural bolting associated with water-control structures-teel pilesrweged forthe stability of the shore barer- and miscellaneous steel associated with these structures. The program addresses age-related deterioration, degradation due to extreme environmental conditions, and the effects of natural phenomena that may affect water-control structures so that the consequences of age-related deterioration and degradation can be prevented or mitigated prior to loss of intended function. The program will be implemented as part of the Structures Monitoring Program (Section A.1.42).

Enclosure to NRC-14-0082 Page 15 B.1.39 RG 1.127, INSPECTION OF WATER-CONTROL STRUCTURES ASSOCIATED WITH NUCLEAR POWER PLANTS Program Description Fermi 2 is not committed to the requirements of NRC RG 1.127, "Inspection of Water-Control Structures Associated with Nuclear Power Plants." However, the program at Fermi 2 was developed based on guidance provided in NRC RG 1.127, Revision 1, and provides an inservice inspection and surveillance program for the Fermi 2 slopes, channels and raw water-control structures associated with emergency cooling water systems or flood protection. The scope of the Fermi 2 program includes water-control structures within the scope of license renewal as delineated in 10 CFR 54.4. The program performs periodic visual examinations to monitor the condition of water-control structures and structural components, including structural steel and structural bolting associated with water-control structures, steel piles requied4 44he sta lit the she ier, and miscellaneous steel associated with these structures. The Fermi 2 program addresses age-related deterioration, degradation due to extreme environmental conditions, and the effects of natural phenomena that may affect water-control structures. The program requires periodic monitoring and maintenance of water-control structures so that the consequences of age-related deterioration and degradation can be prevented or mitigated in a timely manner. The program will be implemented as part of the Structures Monitoring Program (Section B.1.42).

Enclosure to NRC-14-0082 Page 16 RAI B.1.42-1

Background:

Section 54.21(a)(3) of 10 CFR requires the applicantto demonstrate that the effects of agingfor structures and components will be adequately managed so that the intendedfunction(s) will be maintainedconsistent with the CLB for the periodof extended operation. As describedin SRP-LR, an applicantmay demonstrate compliance with 10 CFR 54.21(a)(3) by referencing the GALL Report and when evaluation of the matter in the GALL Report applies to the plant.

LRA Sections B.1.42, "StructuresMonitoring," B. 1.22, "Inservice Inspection-IWF," andB. 1.12, "ContainmentInservice Inspection-IWE," state that the programsare existingprograms that, following enhancement, will be consistent with GALL Report AMPs XI S6, XI S3, andXI S. The "preventiveactions," "parametersmonitored or inspected," and "detection of aging effects" program elements of GALL ReportAMP XI S6, XI S3, andXI Si, as applicable,explicitly address the aging management ofASTMA325, ASTM F1852, andASTMA490 structural bolting. However, during the AMP audit, the staff reviewed the LRA AMPs basis documentsfor the StructuresMonitoringProgram,Inservice Inspection-IWF,and Containment Inservice Inspection-IWE, and noted that the program elements, with enhancements, addressASTMA325 andA490 bolting, but made no mention ofASTM F1852 bolting.

Issue:

It is not clear that the "preventive actions," "parametersmonitored or inspected," and "detection of aging effects" program elements of LRA Section B.1.42; "preventiveactions," and "detection of aging effects" program elements of LRA Section B. 1.22; and the "preventive actions" program element of LRA Section B.1.12 are consistent with the recommendations in GALL Report AMPs XI S6, XI S3, andXI S1, because there was no mention ofASTM F1852 bolting.

Request:

1. State whether ASTMF1852 structuralbolting is used in Fermi 2 structures and is within the scope of license renewal.

2. IfASTMF1852 structuralbolting is within the scope of license renewal, state how the effects of aging will be adequately managedfor the periodof extended operation.

Response

ASTM F1852 bolts are twist-off type tension control structural bolt/nut/washer assemblies. The Fermi 2 plant does not use ASTM F1852 structural bolting. This was verified by reviewing site structural steel specifications, site bolting and torquing procedures, the site WebARMS document

Enclosure to NRC-14-0082 Page 17 search system, the site materials management system, and the site nuclear inventory system (for inventory and purchasing history of such bolts).

Additionally, plant personnel in the Material Engineering Group (MEG), Plant Support Engineering (PSE - the design authority), and Nuclear Engineering were consulted as to the use of this type of bolt in the plant. Among those consulted, there is no knowledge of the use of this type of bolt anywhere in the plant.

As demonstrated above, ASTM F1852 structural bolting is not used at the Fermi 2 plant and is therefore not included in the Structures Monitoring Program in License Renewal Application (LRA) Section B.1.42.

LRA Revisions:

None.

Enclosure to NRC-14-0082 Page 18 RAI B.L.42-2

Background:

Section 54.21(a)(3) of 10 CFR requires the applicantto demonstrate that the effects of agingfor structuresand components will be adequately managedso that the intendedfunction will be maintainedconsistentwith the CLBfor the period of extended operation. As describedin SRP-LR, an applicantmay demonstrate compliance with 10 CFR 54.21(a)(3) by referencing the GALL Report andwhen evaluation of the matter in the GALL Report applies to the plant.

GALL Report AMPs X1 S6 andXL S7 address the detection of aging effects for inaccessible, below-grade concrete structuralelements, which depends on the plant'sspecific ground water/soil condition. Forplants with non-aggressiveground water/soil, the programs recommend: (a) evaluating the acceptability of inaccessible areas when conditions exist in accessible areasthat could indicate the presence of or result in, degradationto such inaccessible areas and (b) examining representativesamples of the exposed portionsof the below grade concrete, when excavatedfor any reason. Forplants with aggressive ground water/soil (pH< 5.5, chlorides > 500 ppm, or sulfates > 1500ppm) and/orwhere the concrete structuralelements have experienced degradation,the GALL Report recommends a plant specific AMP to manage the concrete aging effects during the period of extended operation.

During the audit, the staffnoted that the LRA AMP basis document indicates that the Fermi 2 concrete structures are subjected to an aggressiveground water/soilenvironment. The staff also noted that in updatedfinal safety analysis report (UFSAR) Table 2.5-16, "ChemicalAnalysis of Ground Water, " the groundwater tested in Fermi 2 hadsulfate content above the 1500 ppm limit stated in the GALL Reportfor aggressive groundwater.

Issue:

LRA Section B.1.42, Structures Monitoring,"statesthat the program is an existingprogram that, following enhancement, will be consistentwith GALL Report AMPs XI S6 andXI S7. However, the proposed enhancement to the "StructuresMonitoring" does not appear to be consistent with the GALL Report recommendationsfor an aggressive water/soilenvironment. Additional information is requested to verify consistency with the GALL Reportfor the detection of aging.

effects in inaccessible, below-grade concrete structuralelements exposed to an aggressive groundwater/soil environment.

Request:

1. Clarify how the enhancementfor the "detection of aging effects" program element is consistent with that described in the GALL Report AMPs XL S6 and XI S7 for inaccessible areas exposed to aggressive ground water/soil.

Enclosure to NRC-14-0082 Page 19

2. If criteria other than that described in the GALL Report are being used, provide the basis to justify the adequacy of the proposed exception to manage the aging effects in inaccessible areas.

Response

1. The NUREG-1801 Generic Aging Lessons Learned (GALL) Report Sections XI.S6 and XI.S7 state that for plants with aggressive groundwater/soil (pH<5.5, chlorides >500 ppm, or sulfates-> 1500 ppm) and/or where the concrete structural elements have experienced degradation, a plant-specific aging management program (AMP) accounting for the extent of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation for inaccessible below-grade concrete structural elements.

The Fenni 2 License Renewal Application (LRA) Section B.1.42 "Structures Monitoring" enhancement for the "Detection of Aging Effects" states (as modified in the response to RAI 3.5.2.2.2.1-1 in letter NRC-14-0070 dated October 24, 2014):

"If normally inaccessible areas become accessible due to plant activities, an inspection of these areas shall be conducted. Additionally, inspections will be performed of inaccessible areas in environments where observed conditions in accessible areas indicate that significant degradation may be occurring in the inaccessible areas."

Fermi 2 LRA Table 3.5.1 "Structures and Component Supports" item number 3.5.1-67 is the item that is consistent with the component type and aging effect/mechanism that are discussed in this RAI. The item 3.5.1-67 component is "concrete" and aging effect/mechanism is "Increase in porosity and permeability; cracking; loss of material (spalling, scaling) due to aggressive chemical attack."

The 3.5.2-X tables within the Fermi 2 LRA represent the "Summary of Aging Management Evaluation" for the various structures on site. Cross-referencing the 3.5.1-67 item mentioned above within these 3.5.2-X tables, it can be seen that each resulting item contains the same Material (Concrete) and the same Aging Effect Requiring Management (Increase in porosity and permeability, cracking, loss of material (spalling, scaling)). The one parameter that varies in the 3.5.2-X tables is the Environment in which the concrete is experiencing the same aging effect. It is recognized in the 3.5.2-X tables that concrete above-grade (accessible areas) exposed to an air-outdoor environment experiences the same aging effect requiring management as concrete below-grade (inaccessible areas) exposed to a soil environment. It is also recognized that Table 3.0-2 of the LRA defines air-outdoor as being an environment that may contain aggressive chemical species including chlorides, oxygen, halides, sulfates, or other aggressive corrosive substances that can influence the nature, rate, and severity of corrosion effects. The fact that the accessible concrete exposed to air-outdoor experiences the same aging effect requiring management as the inaccessible concrete exposed to a soil environment provides additional supporting evidence that performing inspections of these accessible areas provides an indication of the condition of the inaccessible structure. This is consistent with the enhancement.

Enclosure to NRC-14-0082 Page 20 DTE reviewed site operating experience (OE), including corrective action program documents and Structures Monitoring Program findings, and observations from recent site modifications (fire protection valve excavations, Emergency Diesel Generator (EDG) feeder cable mod excavations, Independent Spent Fuel Storage Installation (ISFSI) transfer pad excavations, buried pipe inspection excavations) where inaccessible below-grade concrete structural elements became accessible. No instances of structural degradation of below-grade normally inaccessible concrete structures or accessible structures exposed to the same environment/aging effect were identified that indicate that there is significant degradation of the below-grade inaccessible concrete structures exposed to soil / groundwater. This OE indicates that the Structures Monitoring Program at Fermi 2, with enhancements, is consistent with GALL Report Section XI.S6 and is adequate to manage the effects of aging on inaccessible concrete exposed to groundwater.

The Structures Monitoring Program described in LRA Section B.1.42 is appropriate to serve as the plant-specific aging management program accounting for the extent of degradation experienced on concrete structural elements exposed to groundwater at Fermi 2. This is consistent with the recommendations for detection of aging effects in the GALL Report Sections XLS6 and XI.S7.

2. Criteria other than that described in the GALL Report are not being used.

LRA Revisions:

None.

Enclosure to NRC-14-0082 Page 21 RAI B.1.42-3

Background:

Section 54.21(a)(3) of10 CFR requires the applicantto demonstrate that the effects of agingfor structures and components will be adequately managed so that the intendedfunction will be maintainedconsistent with the CLB for the period of extended operation. As describedin SRP-LR, an applicantmay demonstrate compliance with 10 CFR 54.21(a)(3) by referencing the GALL Report and when evaluation of the matter in the GALL Report applies to the plant.

LRA Section B.1.42, "StructuresMonitoring," states that the program is an existing program that,following enhancement, will be consistent with GALL Report AMP XI. S6. LRA Section B. 1.42 includes enhancements to the "parametersmonitoredor inspected," "detection of aging effects," and "acceptance criteria"program elements to revise procedures to meet the guidelinesprovided in American Concrete Institute Standard(ACI)349.3R, to demonstrate consistency with the GALL Report. Duringthe audit, the staffnoted that the program basis document references the 1996 edition ofACI 349.3R. However, the staff notes that GALL Report.

AMP X1 S6 is based on, andreferences, the 2002 edition ofACI 349.3R.

Issue:

Based on the deviation in edition of the referencedACI 349.3R industry standard,it is not clear that LRA AMP B. 1.41 is consistent with GALL Report AMP XI S6. Substantive differences exist between the versions, particularlythe requirementsfor qualificationsofpersonnel. The staff notes that the program enhancements do not reference a specific version; however, the reference to the 1996 version of ACI 349.3R introducespotential inconsistencieswith the GALL Report AMP XZ S6 recommendations.

Request:

1. Describe how inconsistenciesbetween the ACI 349.3R version referenced in the program basis document and the GALL Report are being addressedto demonstrate consistency with the GALL Report recommendations.

2. Otherwise,provide technicaljustificationfor the exception to the GALL Report recommendations.

Response

1. The intent of not referencing a specific version of American Concrete Institute (ACI) 349.3R in the program basis document is to allow for the use of the latest version of ACI 349.3R during development of program implementing procedures. During review of the Fermi 2 Structures Monitoring Program against the program description in NUREG-1801 Generic Aging Lessons Learned (GALL) Report Section XI.S6, the provisions of the 2002 version of

Enclosure to NRC-14-0082 Page 22 ACI 349.3R were considered to assess consistency with the NUREG-1801 aging management program. For clarification, the Fermi 2 Structures Monitoring Program enhancements referencing ACI 349.3R will be revised to specifically indicate use of the 2002 or later version. The revisions to the License Renewal Application (LRA) are indicated below.

2. There are no exceptions being taken to the GALL Report recommendations.

LRA Revisions:

LRA Sections A.1.42, A.4, and B.1.42 are revised as shown on the following pages. Additions are shown in underline and deletions are shown in strike-through.

Enclosure to NRC-14-0082 Page 23 A.1.42 Structures Monitoring Program

" Revise plant procedures to include the following parameters to be monitored or inspected:

> For concrete structures, base inspections on quantitative requirements of industry codes (i.e., ACI 349.3R-02 or later), standards and guidelines (i.e., ASCE 11) and consideration of industry and plant-specific operating experience.

Revise plant procedures to include the following for detection of aging effects:

> Personnel (Inspection Engineer and Program Administrator or Responsible Engineer) involved with the inspection and evaluation of structures and structural components, including masonry walls and water-control structures, meet the qualifications guidance identified in ACI 349.3R-02 or later.

Revise plant procedures to prescribe quantitative acceptance criteria based on the quantitative acceptance criteria of ACI 349.3R-02 or later and information provided in industry codes, standards, and guidelines including ACI 318, ANSI/ASCE 11, and relevant AISC specifications. Industry and plant-specific operating experience will also be considered in the development of the acceptance criteria.

Enclosure to NRC-14-0082 Page 24 A.4 LICENSE RENEWAL COMMITMENT LIST Implementation No. Program or Activity Commitment Schedule Source 34 Structures Monitoring Enhance Structures Monitoring Program as follows: Prior to September A. 142 20, 2024

g. Revise plant procedures to include the following parameters to be monitored or inspected:

e For concrete structures, base inspections on quantitative requirements of industry codes (i.e., ACI 349.3R-02_orater),

standards and guidelines (i.e., ASCE 11) and consideration of industry and plant-specific operating experience.

j. Revise plant procedures to include the following for detection of aging effects:

Personnel (Inspection Engineer and Program Administrator or Responsible Engineer) involved with the inspection and evaluation of structures and structural components, including masonry walls and water-control structures, meet the qualifications guidance identified in ACI 349.3R-02 or later.

k. Revise plant procedures to prescribe quantitative acceptance criteria based on the quantitative acceptance criteria of ACI 349.3R-02 or later and information provided in industry codes, standards, and guidelines including ACI 318, ANSI/ASCE 11, and relevant AISC specifications. Industry and plant-specific operating experience will also be considered in the development of the acceptance criteria.

Enclosure to NRC-14-0082 Page 25 B.1.42 STRUCTURES MONITORING Program Description The Structures Monitoring Program provides for aging management of structures and structural components, including structural bolting, within the scope of license renewal. The program was developed based on guidance in RG 1.160, Revision 2, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," and NUMARC 93-01, Revision 2, "Industry Guidelines for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," to satisfy the requirement of 10 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." The scope of the Structures Monitoring Program includes structures within the scope of license renewal as delineated in 10 CFR 54.4. The scope of the program also includes the condition monitoring of masonry walls and water-control structures as described in the Masonry Wall Program (Section B.1.25) and in the NRC RG 1.127, "Inspection of Water-Control Structures Associated with Nuclear Power Plants," aging management program (Section B.1.39).

The structures and structural components are inspected by qualified personnel. Concrete structures are inspected for indications of deterioration and distress, using guidelines provided in ACI 201.1 R, "Guide for Making a Condition Survey of Existing Buildings," and ACI 349.3R-02 or later, "Evaluation of Existing Nuclear Safety-Related Concrete Structures." Masonry walls are inspected for cracking. Elastomers will be monitored for hardening, shrinkage and loss of sealing. Rock/stone embankment structures will be inspected for loss of material and loss of form. Component supports will be inspected for loss of material and reduction in anchor capacity due to local concrete degradation. Exposed surfaces of bolting are monitored for loss of material and loose or missing nuts and bolts. The program is augmented by plant procedures to ensure that the selection of bolting material, installation torque or tension, and the use of lubricants and sealants are appropriate for the intended purpose. These procedures will be enhanced to include the guidance of NUREG-1339 and EPRI TR-104213, NP-5067, and NP-5769 to ensure proper specification of bolting material, lubricant, and installation torque.

Enclosure to NRC-14-0082 Page 26 B.1.42 STRUCTURES MONITORING Element Affected Enhancement

3. Parameters Monitored or Revise plant procedures to include the following Inspected parameters to be monitored or inspected:

For concrete structures, base inspections on quantitative requirements of industry codes (i.e., ACI 349.3R-02 or later), standards and guidelines (i.e., ASCE 11) and consideration of industry and plant-specific operating experience.

4. Detection of Aging Effects Revise plant procedures to include the following:

Personnel (Inspection Engineer and Program Administrator or Responsible Engineer) involved with the inspection and evaluation of structures and structural components, including masonry walls and water-control structures, meet the qualifications guidance identified in ACI 349.3R-02 or later.

6. Acceptance Criteria Revise plant procedures to prescribe quantitative acceptance criteria based on the quantitative acceptance criteria of ACI 349.3R-02 or later and information provided in industry codes, standards, and guidelines including ACI 318, ANSI/ASCE 11 and relevant AISC specifications. Industry and plant-specific operating experience will also be considered in the development of the acceptance criteria.

Enclosure to NRC-14-0082 Page 27 RAI B.1.42-4

Background:

Section 54.21(a)(3) of 10 CFR requires the applicantto demonstrate that the effects of agingfor structuresand components will be adequately managedso that the intendedfunction(s) will be maintainedconsistent with the CLBfor the period of extended operation. As described in SRP-LR, an applicantmay demonstrate compliance with 10 CFR 54.21(a)(3) by referencing the GALL Report and when evaluation of the matter in the GALL Report applies to the plant.

LRA Section B.1. 39, "RG 1.127, Inspection of Water-ControlStructuresAssociatedwith Nuclear Power Plants," which is implemented by the applicantas part of LRA Section B. 1. 42, "Structures Monitoring," states that the programs are existing programsthat,following enhancement, will be consistent with GALL Report AMPs XI S6 and XI S7. The "parameters monitoredor inspected," "detection of aging effects, " and "acceptance criteria"program elements of GALL Report AMPs XI S6 and XL S7, explicitly addressthe agingmanagement of high-strength (measuredyield strength > 150 ksi) structuralbolts greaterthan 1 inch in diameter. The GALL Report recommends that visual inspections of high-strengthstructural bolts be supplemented with volumetric or surface examinations to detect cracking.

Based on a review of information in the LRA andprovided during the AMP audit, the staff noted that sufficient information was not provided to determine whether high-strengthstructuralbolts (other than ASTMA325, F1852, andA490 used in civil structures)are used in the structuresand how stress corrosioncracking (SCC) will be managed by the AMP(s).

Issue:

It is not clear if there are high strength structuralbolts used in Fermi 2 structures (otherthan ASTMA325, F1852, andA490 used in civil structures) and, if used, whether the "preventive actions," "parametersmonitoredor inspected," and "detection of aging effect" program elements of LRA Sections B.1.42 and B. 1.39 are consistentwith the recommendations in GALL Report AMPs XL S6 and XI S7 regardingthe provision to monitorfor stress corrosion cracking in high strength structuralbolts greater than 1 inch in diameter through supplemental volumetric or surface examinations to detect cracking.

Request:

1. State whether high-strength (measuredyield strength ? 150 ksi) structural bolts greaterthan 1 inch in diameter are used in Fermi 2 structures (includingthose within the scope of the StructuresMonitoringProgramand RG 1.127, Inspection of Water-ControlStructures Associated with Nuclear Power PlantsProgram).

2. If high-strength structuralbolts greaterthan 1 inch in diameter are used (other than ASTM A325, F1852, and A490 used in civil structures), state how the "preventive actions,"

Enclosure to NRC-14-0082 Page 28 "parameters monitored or inspected," and "detection of aging effects" program elements are consistent with the GALL Report recommendations to monitorfor SCC through supplemental volumetric or surface examinations.

Response

High-strength (measured yield strength greater than or equal to 150 ksi) structural bolts greater than 1 inch in diameter are not used in Fermi 2 structures within the scope of the Structures Monitoring Program and RG 1.127 Program with the exception of identified high-strength bolting utilized in the drywell stabilizer assembly with a diameter of 1-3/8". These 1-3/8" diameter bolts are type ASTM A325 bolting. As is identified in the NUREG-1801 Generic Aging Lessons Learned (GALL) Report, bolting type ASTM A325 used in civil structures is one of the material types not prone to stress corrosion cracking (SCC) and is therefore excluded from SCC supplemental monitoring.

Therefore, DTE has identified no high-strength structural bolts greater than 1 inch in diameter (other than ASTM A325, F1852, and A490) that have been utilized in structural applications in structures within the scope of the Structures Monitoring Program and RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants Program.

LRA Revisions:

None.

Enclosure to NRC-14-0082 Page 29 RAI 3.5.2.2.22-

Background:

Section 54.21(a)(3) of 10 CFR requires the applicantto demonstrate that the effects of agingfor structures and components will be adequately managed so that the intendedfunction(s) will be maintainedconsistentwith the CLBfor the period of extended operation. As described in SRP-LR, an applicantmay demonstrate compliance with 10 CFR 54.21(a)(3) by referencingthe GALL Report and when evaluation of the matter in the GALL Report applies to the plant.

SRP-LR Section 3.5.2.2.2.2 addresses reduction of strength and modulus of concrete structures due to elevated temperatures andstates that the GALL Report recommendsfurther evaluation of a plant-specificprogram if any portion of the safety-relatedand other concrete structures exceeds temperature limits of more than 150 degrees Fahrenheit(F) for generalareas and more than 2000F for local areas. The SRP-LR also states that higher temperatures may be allowed if tests and/or calculationsare provided to evaluate the reduction in strength and modulus of elasticity and these reductionsare applied to the design calculations.

LRA Table 3.5.1, item 48, states that reduction of strength and modulus due to elevated temperatures do not require aging managementfor Fermi 2 Group 1-5 concrete structures.

However, the further evaluation, LRA Section 3.5.2.2.2.2, states that the Structures Monitoring Program manages this aging effect for the main steam tunnel in the turbine building since the general temperature in this area exceeds 150YF during normal operation.

Issue:

Based on the informationprovided in the LRA, it is not clear how the StructuresMonitoring Program is adequate to manage the "changes in materialproperties" due to elevated temperaturesfor Fermi 2 Group 1-5 concrete structures, and/or whether a reduction in strength and modulus of elasticitywhere appliedto the design calculationsbased on tests and/or calculationsthat evaluates these reductionsdue to the elevated temperatures.

Request:

1. State whether a reduction in strength and modulus of elasticity was applied in the design calculationsof Fermi 2 Group 1-5 concrete structures exposed to general area temperatures above 150For local area temperatures above 200F.

2. If a reduction in strength and modulus of elasticity was not applied in the design calculations,explain how the Structures MonitoringProgramwill adequately manage this aging effect.

Enclosure to NRC-14-0082 Page 30

Response

I. A reduction in strength and modulus of elasticity was not applied in the design calculations of Fermi 2 Group 1-5 concrete structures exposed to general area temperatures above 150°F or local area temperatures above 200F.

2. The Structures Monitoring Program will adequately manage the aging effect of reduction of strength and modulus of elasticity due to elevated temperature. The specific aging effects addressed are loss of material, cracking and change in material properties. The parameter monitored by the Structures Monitoring Program to manage reduction of strength and modulus of elasticity is the condition of the exposed concrete surface. Acceptance criteria include the absence of spalling, cracking, and other physical damage, consistent with the parameters identified in American Concrete Institute (ACI) 349.3R-02 for concrete degradation due to thermal exposure. Failure to meet the acceptance criteria is cause for documenting the condition in DTE's corrective action program for further evaluation, which may include other examination. In order to clarify that Group 1-5 concrete structures are not exposed to temperatures that exceed the threshold, with the exception of the main steam tunnel, and that the Structures Monitoring Program will manage reduction of strength and modulus due to elevated temperature for the main steam tunnel in the turbine building, the License Renewal Application (LRA) will be revised as indicated below. Note that LRA Table 3.5.2-3 does already indicate that the Structures Monitoring Program is used to manage this aging effect for the main steam tunnel (pipe tunnel).

LRA Revisions:

LRA Table 3.5.1 (item 3.5.1-48) is revised as shown on the following page. Additions are shown in underline and deletions are shown in strike-through.

Enclosure to NRC-14-0082 Page 31 Table 3.5.1: Structures and Component Supports Aging Further Item Aging Effect/ Management Evaluation Number Component Mechanism Programs Recommended Discussion 3.5.1-48 Group 1-5: Reduction of A plant-specific Yes, if Listed-agingeffeGtsde concrete: all strength and aging temperature not-require modulus due to management limits are managemen-tat elevated program is to exceeded Fermi-2-Fermi 2 temperature be evaluated. concrete in areas for

(>150°F general; this grouping are not

>200*F local) exposed to temperatures that exceed the thresholds, with the exception of the main steam tunnel of the turbine building.

For the main steam tunnel, the Structures Monitoring Program manages this aaing effect.

For further evaluation, see Section 3.5.2.2.2.2.

Enclosure to NRC-14-0082 Page 32 RAI 3.5.L 83-1

Background:

Section 54.21(a)(3) of 10 CFR requires the applicantto demonstrate that the effects of agingfor structures and components will be adequately managed so that the intendedfunction(s) will be maintainedconsistent with the CLB for the period of extended operation. As described in SRP-LR, an applicantmay demonstrate compliance with 10 CFR 54.21(a)(3) by referencing the GALL Report and when evaluation of the matter in the GALL Report applies to the plant.

LRA Table 3.5.2-4 identifies stainlesssteel anchor bolts exposed to a fluid environmentfor water-controlstructures as "Note A" to indicate that this item is consistent with the GALL Report item IH A6. TP-221. However, GALL Report item IIIA6. TP-221 addresses steel structuralbolting when exposed to several environments.

Per the material definition in GALL Report Chapter IX C, stainless steel is considereda different categoryfrom the steel category. These two materialcategories exposed to certain environments may experience different aging effects/mechanism. The GALL Report states that crackingdue to SCC can occur in austeniticstainless steel at ambient temperature ifthere is a harsh environment, at temperatures above 140°F (60 degrees Celsius), or where an environment with stagnant,oxygenated boratedwater systems is present. LRA Table 3.5.2-4 indicates that the stainless steel anchor bolts are exposed to afluid environment andstates that the aging effect requiringmanagement is loss of material. However, the LRA environment descriptionfor "Exposed to FluidEnvironment" correspondsto a broadlist of environment types that includes environments with treated water and/or treatedwater with temperature above 140F which makes a stainless steel materialsusceptible to SCC.

Issue:

Based on the information in the LRA, it is not clear if the stainless steel anchor bolts listed in LRA Table 3.5.2-4 are exposed to an environment conducive to SCC.

Request:

1. Describe the fluid environment to which these anchor bolts are exposed including temperature and water chemistry.

2. If the anchor bolts are in an environment conducive to SCC, state how the RG 1.127, Inspection of Water-ControlStructuresAssociated with Nuclear Power PlantsAMP will adequately manage this aging effect.

Enclosure to NRC-14-0082 Page 33

Response

1. The fluid environment to which the stainless steel anchor bolts listed in License Renewal Application (LRA) Table 3.5.2-4 are exposed is water from Lake Erie described as raw water in LRA Table 3.0-2. The temperature of this water is < 140°F. In general, the evaluation of aging effects in the LRA assumes that Lake Erie water has similar water chemistry as the groundwater. In this case, based on a water quality study performed over a one year period from 2008 to 2009 (Table 2 of ML093380411), the following key water chemistry parameters of the Lake Erie water are utilized for the evaluation of aging effects.

pH: 7.57 to 8.88 Chlorides: 18.1 to 38.0 ppm Sulfate: 28.3 to 32.5 ppm Sodium: 9.75 to 20.6 ppm Calcium: 33.5 to 41.9 ppm Magnesium: 9.09 to 11.5 ppm

2. The stainless steel anchor bolts listed in LRA Table 3.5.2-4, exposed to fluid environment, are not in an environment conducive to stress corrosion cracking (SCC). Consistent with NUREG-1801 Generic Aging Lessons Learned (GALL) Report Chapter IX, Section D, SCC at temperatures less than 140°F (60°C) is not expected in the absence of a harsh environment (significant presence of halogens, specifically chlorides).

SCC of these stainless steel anchor bolts is not credible at temperatures below 140°F (60°C) because they are not exposed to an environment with a significant presence of contaminants, specifically chlorides. The normal operating temperature of the fluid environment to which these anchor bolts are exposed is less than the SCC threshold temperature of 140°F.

Therefore, cracking due to SCC is not an aging effect requiring management for the stainless steel anchor bolts exposed to fluid environment.

LRA Revisions:

None.

Enclosure to NRC-14-0082 Page 34 RAI 3.5.2.3.2-1

Background:

Section 54.21(a)(3) of 10 CFR requires the applicantto demonstrate that the effects of agingfor structures andcomponents will be adequately managedso that the intendedfunction(s) will be maintainedconsistent with the CLB for the periodof extended operation. As described in SRP-LR, an applicantmay demonstrate compliance with 10 CFR 54.21(a)(3) by referencing the GALL Report and when evaluation of the matter in the GALL Report applies to the plant.

LRA Table 3.5.2-2, states that asbestos cement board exposed to a fluid environment in water-control structures will be managedfor loss of materialby the RG 1.127, Inspection of Water Control StructuresAssociated with Nuclear Power Plants Program. LRA Table 3.0-2 describes the fluid environmentfor structures at Fermi 2 as either raw water or treatedwater with various temperatures.

GALL Report Table IX C describes asbestos cement as a cementitious materialand defines it as any material having cementingproperties,which contributes to the formation of hydrated calcium silicate compounds. GALL Report Table IX F also describes different aging mechanisms like abrasion,aggressive chemical attack, leachingof calcium hydroxide and carbonationwhich, depending on the type of environment and its aggressiveness, can lead to aging effects such as increase in porosity andpermeability, cracking, loss of material(spalling, scaling), loss of strength, among others,for similar cementitious materials.

Issue:

Based on the informationprovided in the LRA, it is not clear to which type offluid environment the asbestos cement boardis exposed (e.g., raw water, treatedwater) and whether all applicable aging effects/mechanism for this cementitious materialexposed to thatfluid environment are being adequately managed.

Request:

1. Describe the fluid environment to which the asbestos cement boardis exposed (i.e., raw water, treatedwater), including the water chemistry.

2. Consideringthe environment to which the asbestos cement board is exposed, explain why other agingeffects relatedto cementitious materials (e.g., increase in porosity and permeability,cracking,and loss of strength) are not consideredcredible aging effects.

Response

1. The fluid environment to which the asbestos cement board residual heat removal (RHR) cooling tower fill/mist eliminators listed in License Renewal Application (LRA)

Enclosure to NRC-14-0082 Page 35 Table 3.5.2-2 are exposed is described as raw water in LRA Table 3.0-2 and the source is Lake Erie water. The temperature of this water is < 140°F. The following are key water chemistry parameters of the Lake Erie water (see response to RAI 3.5.1.83-1 for discussion of the source of these parameters).

pH: 7.57 to 8.88 Chlorides: 18.1 to 38.0 ppm Sulfate: 28.3 to 32.5 ppm Sodium: 9.75 to 20.6 ppm Calcium: 33.5 to 41.9 ppm Magnesium: 9.09 to 11.5 ppm Although the source of water in the RHR reservoir (to which the asbestos cement board is exposed) is Lake Erie water as indicated above, the water is chemically treated for control of microbes, corrosion, and deposits. The water chemistry of this water is then monitored to be maintained within specified chemistry parameters. For example, the specification limit on chlorides in this water is 100 ppm. A water chemistry sample from 2013 indicated a pH of 8.0, chloride of 85 ppm, sulfate of 71 ppm, and sodium of 61 ppm. Although in some cases these values are above the ranges of the original Lake Erie water indicated above, the chloride and sulfate values are well below the thresholds for aggressive chemical attack discussed in the NUREG-1801 Generic Aging Lessons Learned (GALL) Report.

2. Credible aging effects for the asbestos cement board RHR cooling tower fill/mist eliminators do not include: cracking, loss of bond and loss of material (spalling, scaling) due to corrosion of embedded steel since this component does not have embedded steel; and cracking due to expansion from reaction with aggregates since this component does not have aggregate.

However, credible aging effects do include: loss of material (spalling, scaling) and cracking due to freeze-thaw; and loss of material (due to abrasion). Loss of material is already included in LRA Table 3.5.2-2 as an applicable aging effect. For consistency with application of aging effects to concrete components, additional aging effects of cracking and increase in porosity and permeability and loss of strength will be included for the asbestos cement board RHR cooling tower fill/mist eliminators. The revisions to the LRA are indicated below.

LRA Revisions:

LRA Table 3.5.2-2 is revised as shown on the following page. Additions are shown in underline and deletions are shown in strike-through.

Enclosure to NRC-14-0082 Page 36 Table 3.5.2-2 Water-Control Structures Summary of Aging Management Review Table 3.5.2-2: Water-Control Structures Structure and/or Aging Effect Aging Component or Intended Requiring Management NUREG- Table 1 Commodity Function Material Environment Management Programs 1801 Item Item Notes RHR cooling SSR Asbestos Exposed to Cracking, Loss RG 1.127 J tower fill/mist cement fluid of material eliminators board environment RHRcpoling SSR Asbestos Expogsed to Increase in RG 1.127 tower fijj/mist cement fluid porosity and eliminators board environment eprmeability:

Loss of strendgth Barrier stone FLB, SSR Rock/ Air - outdoor/ Loss of material; RG 1.127 Ill.A6.T-22 3.5.1-58 A stone Exposed to Loss of form fluid environment