ML081000278
| ML081000278 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/27/2008 |
| From: | Office of Nuclear Reactor Regulation |
| To: | Division of License Renewal |
| References | |
| Download: ML081000278 (5) | |
Text
From:
Bo Pham To:
"Donna Tyner" <dtyner@entergy.com>,"MICHAEL D STROUD"
<MSTROUD@entergy.com>
Date:
3/27/2008 5:08:38 PM
Subject:
DRAFT RAIs on TIME-LIMITED AGING ANALYSES, BOLTED CONNECTIONS, AND BORAFLEX cc:
"Kimberly Green" <KJG1@nrc.gov>,<IPNonPublicHearingFile@nrc.gov>
Donna and Mike, Attached is a draft request for additional information related to the Indian Point license renewal application. Please review and let me know when Entergy is available to discuss. The purpose of the telecon will be to obtain clarification on the staff's questions.
- Thanks, Bo Pham Sr. Project Manager Division of License Renewal U.S. Nuclear Regulatory Commission 301-415-8450 O-11C12 bmp@nrc.gov
Hearing Identifier:
IndianPointUnits2and3NonPublic Email Number:
452 Mail Envelope Properties (47FCAC58.HQGWDO01.OWGWPO04.200.2000006.1.18021E.1)
Subject:
DRAFT RAIs on TIME-LIMITED AGING ANALYSES, BOLTED CONNECTIONS, AND BORAFLEX Creation Date:
3/27/2008 5:08:38 PM From:
Bo Pham Created By:
BMP@nrc.gov Recipients "Kimberly Green" <KJG1@nrc.gov>
<IPNonPublicHearingFile@nrc.gov>
"Donna Tyner" <dtyner@entergy.com>
"MICHAEL D STROUD" <MSTROUD@entergy.com>
Post Office Route OWGWPO04.HQGWDO01 nrc.gov Files Size Date & Time MESSAGE 435 3/27/2008 5:08:38 PM TEXT.htm 789 4/9/2008 11:45:28 AM Draft RAIs TLAA and AMPs 03-27-08.doc 50688 4/9/2008 11:45:28 AM Options Priority:
Standard Reply Requested:
No Return Notification:
None None Concealed
Subject:
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Standard
Donna and Mike, Attached is a draft request for additional information related to the Indian Point license renewal application. Please review and let me know when Entergy is available to discuss. The purpose of the telecon will be to obtain clarification on the staff's questions.
- Thanks, Bo Pham Sr. Project Manager Division of License Renewal U.S. Nuclear Regulatory Commission 301-415-8450 O-11C12 bmp@nrc.gov Page 1 of 1 4/9/2008 file://c:\\EMailCapture\\IndianPointUnits2and3NonPublic\\452\\attch1.htm
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI)
TIME-LIMITED AGING ANALYSES, BOLTED CONNECTIONS, AND BORAFLEX Time-Limited Aging Analyses D-RAI 4.3.1.8-1 License Renewal Application Section 4.3.1 states Current design basis fatigue evaluations calculate cumulative usage factors (CUFs) for components or sub-components based on design transient cycles. For CUF values listed in LRA Tables 4.3-13 and 4.3-14, please provide the methodology used with sufficient results of the fatigue analysis such that the staff can make a determination based on the guidance described in Standard Review Plan-License Renewal (SRP-LR) (NUREG-1800). Specifically, please describe the details of how environmentally assisted fatigue (EAF) is factored into the calculation of the CUF using Fen values.
D-RAI 4.3.1.8-2 From the review of EAF analysis of other plants, it was found that the transfer function methodology used in the EAF analysis may not provide valid results as it is dependent on the inputs. To assist the staff in its review, please provide the EAF analysis for all the NUREG/CR-6260 locations (components) at Indian Point unless it can be demonstrated that the CUF value is within the ASME Code limit of 1.0 by using the original 40-year analysis value adjusted for 60 years and multiplied by Fen, which is consistent with SRP-LR and ASME Code. This analysis should be completed by using NRC-approved fatigue software and the ASME Code,Section III, Subsection NB-3200 methodology (which defines the use of six stress components to determine the stress state and thereby calculates the principal stresses and stress intensities). Justify the analysis method, the load (stress) combination and the results of the ASME Code analysis if 2-D axis-symmetric modeling is used. In addition, the analysis should apply ASME code rules such as elastic-plastic correction factor, Ke, and stress intensities correction factor for modulus of elasticity. This analysis should be performed without the use of the transfer function method.
D-RAI 4.3.1.8-3 SRP-LR Section 4.3.2.1.1.3 provides the basis for the staff acceptance of an aging management program to address environmental fatigue. It states, [T]he staff has evaluated a program for monitoring and tracking the number of critical thermal and pressure transients for the elected reactor coolant system components. The staff has determined that this program is an acceptable aging management program to address metal fatigue of the reactor coolant system components according to 10 CFR 54.21(c)(1)(iii). The staff is unable to determine if the Fatigue Monitoring Program of IP2 and IP3 contain sufficient details to satisfy this criterion, based on the NA items listed in LRA Tables 4.3-13 and 4.3-14. Please provide adequate details of the Fatigue Monitoring Program, specifically the fatigue analysis used in determining the CUF values for the NA locations and how IPEC plans to proceed in monitoring the locations of Tables 4.3-13 and 4.3-14 during the period of extended operation.
D-RAI 4.3.1.8-4 Section B.1.12 of the LRA amendment dated January 22, 2008, states If ongoing monitoring indicates the potential for a condition outside that analyzed above, IPEC may perform further reanalysis of the identified configuration using established configuration management processes as described above. Please explain in detail what is meant by the phrase using established configuration management processes. Also, please explain in detail the corrective actions and the frequency that such actions will be taken so the acceptance criteria will not be exceeded in the period of extended operation.
Non-EQ Bolted Cable Connection AMP D-RAI 3.0.3.3.6-1 With regard to Indian Point Aging Management Program (AMP) B.1.22, Non-EQ Bolted Cable Connection Program, the license renewal application states that inspection methods may include thermography, contact resistance testing, or other appropriate methods including visual, based on plant configuration and industry guidance. In Generic Aging Lessons Learned (GALL)
AMP XI.E6, the staff recommends thermography, contact resistance testing, or other appropriate methods based on plant configuration and industry guidance for detecting loss of preload or bolt loosening. In the case where visual inspection will be the only method used, provide a technical basis of how this will be sufficient to detect loss of preload or loosening of bolted connections.
Boraflex AMP D-RAI 3.0.3.2.3-1 Indian Point 2 Updated Final Safety Analysis Report, Revision 20, dated 2006, Section 14.2.1 on page 55 of 218, states in part that:
Northeast Technology Corporation report NET-173-01 and NET-171-02 are based on conservative projections of amount of boraflex absorber panel degradation assumed in each sub-region. These projections are valid through the end of the year 2006.
Please confirm that the Boraflex neutron absorber panels in the Indian Point Unit 2 spent fuel pool have been re-evaluated for service through the end of the current licensing period. Also, please discuss the plans for updating the Boraflex analysis during the period of extended operation.