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{{Adams
#REDIRECT [[NL-15-010, Response to Request for Additional Information Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Indian Point Nuclear Generating Unit Number 3]]
| number = ML15034A507
| issue date = 01/26/2015
| title = Response to Request for Additional Information Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Indian Point Nuclear Generating Unit Number 3 (TAC No. MF5148)
| author name = Coyle L M
| author affiliation = Entergy Nuclear Northeast, Entergy Nuclear Operations, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000286
| license number = DPR-064
| contact person =
| case reference number = NL-15-010, TAC MF5148
| document type = Letter
| page count = 5
| project = TAC:MF5148
| stage = Response to RAI
}}
 
=Text=
{{#Wiki_filter:wEntergyEnterciv Nuclear NortheastIndian Point Energy Center450 Broadway, GSBP.O. Box 249Buchanan, NY 10511-0249Tel (914) 254-6700Lawrence CoyleSite Vice PresidentNL-15-010January 26, 2015U.S. Nuclear Regulatory CommissionDocument Control Desk11545 Rockville Pike, TWFN-2 F1Rockville, MD 20852-2738
 
==SUBJECT:==
 
==REFERENCES:==
1.Response to Request for Additional Information Regarding ProposedRevision to Reactor Vessel Surveillance Capsule Withdrawal ScheduleIndian Point Nuclear Generating Unit Number 3 (TAC No. MF5148)Docket No. 50-286License No. DPR-64NRC Letter to Entergy Regarding Request for Additional InformationProposed Revision to Reactor Vessel Surveillance Capsule WithdrawalSchedule (TAC No. MF5148), Dated January 14, 20152. Entergy Letter (NL-14-129) to NRC Regarding Proposed Revision toReactor Vessel Surveillance Capsule Withdrawal Schedule Per 10 CFR50 Appendix H, dated November 5, 2014
 
==Dear Sir or Madam:==
The Nuclear Regulatory Commission (NRC) requested additional information (Reference 1)regarding the Entergy Nuclear Operations Inc. (Entergy) request for a change to the ReactorVessel surveillance capsule withdrawal schedule (Reference 2). The response to the requestedinformation is attached.There are no new commitments in this letter.If you have any questions, or require additional information, please contact Mr. Robert Walpole,Regulatory Assurance Manager, at [914] 254-6710.
NL-15-010Docket No. 50-286Page 2 of 21d~clare under penalty of perjury that the foregoing is true and correct. Executed on January..=L(=, 2015Sincerely,
 
==Attachment:==
Response to Request for Additional Information Regarding ProposedRevision to Reactor Vessel Surveillance Capsule Withdrawal Schedulecc: Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORLMr. Daniel H. Dorman, Regional Administrator, NRC Region 1NRC Resident InspectorMr. John B. Rhodes, President and CEO, NYSERDA w/o Enclosure 2Ms. Bridget Frymire, New York State Dept. of Public Service w/o Enclosure 2 ATTACHMENT TO NL-15-010RESPONSE TO REQUEST FOR ADDITIONAL INFORMATIONREGARDING PROPOSED REVISION TO REACTOR VESSELSURVEILLANCE CAPSULE WITHDRAWAL SCHEDULEENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT NUCLEAR GENERATING UNIT NO. 3DOCKET NO. 50-286 NL-15-010Docket No. 50-286Attachment 1Page 1 of 2REQUEST FOR ADDITIONAL INFORMATIONPROPOSED REVISION TO REACTOR VESSELSURVEILLANCE CAPSULE WITHDRAWAL SCHEDULEBy letter dated November 5, 2014 (Accession No. ML14323A729), Entergy Nuclear Operations,Inc. (Entergy, the licensee) requested approval from the Nuclear Regulatory Commission (NRC)regarding a revision to the reactor vessel surveillance capsule withdrawal schedule pursuant toTitle 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix H, Section III.B.3.The NRC staff has reviewed the proposal and determined that additional information is needed.The NRC staff, Vessels and Internals Integrity Branch (EVIB), requested a response to thefollowing request for additional information.BACKGROUND10 CFR Part 50, Appendix H, states that the purpose of the material surveillance program is tomonitor changes in the fracture toughness properties of ferritic materials in the reactor vesselbeltline region of light water nuclear power reactors which result from exposure of thesematerials to neutron irradiation and thermal environment. Under the program, fracturetoughness test data are obtained from material specimens exposed in surveillance capsules,which are withdrawn periodically from the reactor vessel.ISSUEOut of the capsules that have been removed and tested, capsule Z had the highest fluencevalue at 1.04 x 1019 n/cm2 with a lead factor of 3.48. The most recent capsule tested, which wasremoved in 2003, had a capsule fluence of 8.74 x 1018 n/cm2 with a lead factor of 1.49. Theproposed schedule would postpone the withdrawal and testing of the next capsule until refuelingoutage 23 (currently scheduled for March 2025) which would have a capsule fluence ofapproximately 1.85 x 1019 n/cm2 with a lead factor of 1.52. This fluence would correspond to areactor vessel peak fluence of 1.22 x 1019 n/cm2.REQUESTEstimate when the vessel peak fluence is expected to exceed the fluence of capsule Z. Further,describe how the fluence of the reactor vessel beltline materials will be monitored once thereactor vessel peak fluence surpasses that of capsule Z.RESPONSEBased on current core burnup estimates and the most recent fluence evaluation, Entergyestimates that the peak vessel clad/base metal interface will be subjected to a neutron fluenceof approximately 1.04 x 1019 n/cm2 (i.e. Capsule Z equivalent neutron fluence) at approximately31 Effective Full Power Years (EFPY). Indian Point 3 is currently projected to reach 31 EFPYapproximately in October 2019.
NL-15-010Docket No. 50-286Page 2 of 2After the peak vessel fluence exceeds the fluence of Capsule Z, it will be monitored inaccordance with the requirements of 1OCFR50 Appendix H. Appendix H requires that asurveillance capsule withdrawal schedule be established based on the requirements ofparagraph 7.6.2 and Table 1 from ASTM E-185-82. The Indian Point 3 surveillance capsulewithdrawal schedule proposed in the November 5, 2014 letter implements the requirements ofASTM E-185-82 for a 60 calendar year (48 EFPY) operating term. It should also be noted thatalthough the peak vessel clad/base metal fluence is expected to exceed the fluence of CapsuleZ prior to the withdrawal of the next surveillance capsule, the 1/4 thickness (i.e. the location usedto establish the normal operating heatup and cooldown limits) fluence is not expected to exceedthe Capsule Z fluence prior to the end of the period of extended operation (60 calendar year).
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