L-15-166, Supplemental Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, Reactor Vessel Internals Inspection Plan (TAC No. ME4640) and License Renewal Application Amendment No. 56
| ML15140A705 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/20/2015 |
| From: | Lieb R FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-15-166, TAC ME4640 | |
| Download: ML15140A705 (10) | |
Text
FENOC' ~ 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Raymond A. Lieb 419-321-7676 Vice President, Nuclear Fax: 419-321-7582 May 20, 2015 L-15-166 10 CFR 54 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License Number NPF-3 Supplemental Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1. Reactor Vessel Internals Inspection Plan (TAC No. ME4640) and License Renewal Application Amendment No. 56 By letter dated August 27, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102450565), FirstEnergy Nuclear Operating Company (FENOC) submitted an application pursuant to Title 10 of the Code of Federal Regulations, Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse). By letter dated April 21, 2015 (ML15113B132, ML15113B133, and ML15113B134), FENOCsubmitted the Davis-Besse Reactor Vessel Internals Inspection Plan. Based on a telephone conference call held with the Nuclear Regulatory Commission (NRC) on May 6, 2015, to discuss the Inspection Plan details, attached is supplemental information to support completion of the NRC review of the Plan.
Attachment 1 provides a description of the Davis-Besse Reactor Vessel Internals Inspection Plan supplemental information. Attachment 2 identifies three Regulatory Commitments that are superseded by License Renewal Future Commitments. The Enclosure provides Amendment No. 56 to the Davis-Besse LRA.
Davis-Besse Nuclear Power Station, Unit No. 1 L-15-166 Page 2 There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Clifford I. Custer, Fleet License Renewal Project Manager, at 724-682-7139.
I declare µnder penalty of perjury that the foregoing is true and correct. Executed on May_£, 2015.
Sincerely,
,~Id#
R~0A. Lieb Attachments:
- 1. Davis-Besse Reactor Vessel Internals Inspection Plan Supplemental Information
- 2. Deleted Regulatory Commitments
Enclosure:
Amendment No. 56 to the Davis-Besse License Renewal Application cc: NRC DLR Project Manager NRC Region Ill Administrator cc: w/o Attachments or Enclosure NRC DLR Director NRR DORL Project Manager NRC Resident Inspector Utility Radiological Safety Board
Attachment 1 L-15-166 Davis-Besse Reactor Vessel Internals Inspection Plan Supplemental Information Page 1 of 1 Item 1:
Three Regulatory Commitments were provided by FENOC letter dated April 21, 2015 (ML15113B132, ML15113B133, and ML15113B134). The Commitments are superseded by new License Renewal Future Commitments 52, 53 and 54 as shown in the Enclosure to this letter, Table A-1, Davis-Besse License Renewal Commitments."
The Implementation Schedule date for new License Renewal Future Commitment 54 was revised to October 22, 2016, to align with the completion date for the majority of the other License Renewal Future Commitments.
Item 2:
AREVA NP Inc. document number 51-9191898-000, "Reactor Vessel Internals Welds Stress Relief Records Search for the Operating 177-FA B&W Units," dated October 30, 2012, contains the fabrication records supporting Davis-Besse Reactor Vessel Internals Inspection Plan Action Item #4, detailed in FENOC Letter L-15-139 dated April 21, 2015 (ML15113B132, ML15113B133, and ML15113B134), Enclosure B, AREVA NP Report No. ANP-3285 Revision 0, "Confirmation of Stress Relief for the DB-1 Core Support Shield Upper Flange Weld."
Item 3:
To address Davis-Besse Reactor Vessel Internals Inspection Plan Action Item 8, License Renewal Application (LRA) Sections A.1.32 and B.2.32, both titled, "PWR Reactor Vessel Internals Program," are revised to include a new paragraph, as follows:
Locations using replacement bolts, fabricated from Alloy X-750 material, are the upper core barrel (UCB), the lower core barrel (LCB), lower thermal shield (L TS) and surveillance specimen holder tube (SSHT).
These replacement bolts have cumulative usage factor analyses that are TLAAs and are managed by the PWR Reactor Vessel Internals Program where volumetric UT examinations are performed on a periodic basis consistent with the program's inspection plan.
See the Enclosure to this letter for the revision to the Davis-Besse LRA.
Attachment 2 L-15-166 Superseded Regulatory Commitments Page 1 of 2 The following list identifies three Regulatory Commitments provided by FENOC letter dated April 21, 2015(ML151138132, ML151138133, and ML151138134). The Commitments are superseded by License Renewal Future Commitments as shown in the Enclosure to this letter, Table A-1, Davis-Besse License Renewal Commitments."
Therefore, the three Regulatory Commitments are superseded as shown below.
Regulatory Commitment Due Date
- 1. l.fl ,cespeRse te MR,Q 22 7 A AwlicaRtlbiceRsee l/JlitRiR eRe year ef. #le ActieR #em e, soomit /ef:aflee aRa.'¥ses j1:JstifyiRg detectioR of. /egradatioR
- le accepf:aeillty. of. iRaccessih!e aRd f*ceediRg #le RGR iRspecf:aele cempeReRt items (eofe eaFFel accepf:aRce cfitefia ef eyliR1er iRclt1ding 1t1ef#ca,l aRd cifel:JmfefeRtial the liRked MRP. 227 A seam v1ekJ.s, fe1mer plates, f*tema,l ea#le te pfimary compoReRt ea#le ee#s aRd #leif leclf.ing /e 1rlices, cefe eaffe,l items leadiRg to te fe1mer eo#s aRd #leir ,leckfRg /e'rlices, a Rd expaRsioR iRtema,l ea#le te ea#le ee#sj fer CORtiRl:Jed ope.r:atioR tRmf:lgh #le pefiod of. exteR1ed eperatiOR .fay- peffeFmiRg aR e1rla,ll:JatiOR Of* .fay p.r:eJJesiRg a schefl.l:J!e fer .r:eplacemeRt of. #le compeReRt items (see GR 2()14 ()6427).
- 2. .lfl respoRse te M-R,Q 227 A AwlicaRtlbiceRsee 0Re y-ear pfior te the ActieR ,ttem 7, /e~'elep aRe s1:Jemit a pl-aRt specific MRP227A aRa.'¥sis te /emoRstJ::ate #lat #le lRce,ce inspectieR ef. #le MoRitefi-Rg .lflstFl:JmeRf:atieR (-1-M.9 g1:Ji1e wee awlicaele cempoReRt assemely- spi1e.r:s, GeRtr:el Roe G1:Ji1e Tu.Jae #ems fGRG 71 spacer castiRgs, aRd af/.ditioRal RV IRtemals compoReRt items that may- ee faeficated from GA SS, mafteRsi#c sf:aiR.less steel, or mafteRsi#c p,cecipif:atioR ha.t:deRed stain.less steel matefials (e.g., Ge.r:e Sl:Jf)pefl: Shielfl. fGSS) 'leRt val1gte top aRd eettem .r:ef:aiRiRg fiRgs) wilt maiRf:aiR tReir ft:JRctioRal#y- fl.l:Jfi-Rg #le pefiod of. exteR1ed epe.r:atioR. The aRa.'¥sis Mlill coRsi1er #le possih.le loss of. fracwre te1:Jgtmess in these compenent items fl.l:Je te #le1ma,l emefitf;lemeRt fTE} aRd/ef iffadiatieR emefittlemeRt ~le) aRd may- al-se Reed
L-15-166 Page 2of2 to consider limitations on accessibility for inspection and the resol-utionlsensitivity of the inspection techniques. The Davis Besse analysis will be consistent with the licensing basis and the need to maintain the functionality of the component items being e 1a!uated under all 1
licensing basis conditions of operation.
- 3. ln response to MRP 227 A Applicant/Licensee April 22, 2017 Action ltem 8, update and submit an evaluation for the period of extended operation regarding the effect of irradiation on the mechanical properties and deformation limits of the RV internals that was evaluated for the current term of operation in Appendix E of Topical Reporl BA V'l 10008, Patt 1, Re 1ision 1 supplemented by DB 1 USAR 1
Appendix 41'..
Enclosure Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse)
Letter L-15-166 Amendment No. 56 to the Davis-Besse License Renewal Application Page 1of5 License Renewal Application Sections Affected Section A.1. 32 Table A-1 Section B.2.32 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 A L-15-166 Page 2 of 5 Affected LRA Section LRA Page No. Affected Paragraph and Sentence A.1.32 Page A-21 New 3rd Paragraph To address Davis-Besse Reactor Vessel Internals Inspection Plan Action Item 8, LRA Section A.1.32, "PWR Reactor Vessel Internals Program," previously revised by FENOC letter dated March 9, 2012 (ML12094A383), is revised to include a new third paragraph, as follows:
Locations using replacement bolts. fabricated from Alloy X-750 material. are the upper core barrel (UCB), the lower core barrel (LCB), lower thermal shield (L TS) and swveillance specimen holder tube (SSHT). These replacement bolts have cumulative usage factor analyses that are TLAAs and are managed by the PWR Reactor Vessel Internals Program where volumetric UT examinations are performed on a periodic basis consistent with the program's inspection plan.
Enclosure A l-15-166 Page 3 of 5 Affected LRA Section LRA Page No. Affected Paragraph and Sentence Table A-1 A-69 New Commitments Nos. 52, 53, 54 FENOC Regulatory Commitments DB-l-15-139-1, -2 and -3 are superseded by three license renewal future commitments, and LRA Table A-1, "Davis-Besse license Renewal Commitments," is revised to read as follows:
Table A-1 Davis-Besse License Renewal Commitments Related LRA Item Implementation Commitment Source Section No./
Number Schedule Comments 52 In res12.onse to MRP-227-A A12.12.licant/Licensee Action Item 61 Within one y__ear FENOC A.1.32 submit for NRG review and a12.12.roval an evaluation justify__ing the of the detection of Letters B.2.32 acceg_tability__ of inaccessible and non-ins12.ectable com12.onent items deg_radation L-15-139 (core barrel c'Lfinder including_ vertical and circumferential seam exceeding_ the and welds 1 former 12.lates1 external baffle-to-baffle bolts and their locking acce12.tance L-15-166 devices 1 core barrel-to-former bolts and their locking_ devices 1 and criteria of the internal baffle-to-baffle boltsl for continued 012.eration through the linked 12.eriod of extended 012.eration and1 if necessarv1 12.rovide a 12.lan for MRP-227-A reelacement of the com12.onents. erimarv com12.onent items leading_ to ex12.ansion 53 In res12.onse to MRP-227-A A12.12.licant/Licensee Action Item 71 One y__ear 12.rior to FENOC A.1.32 develo12. and submit for NRG review and a12.12.roval a 12.lant-s12.ecific the MRP-227-A Letters B.2.32 analy__sis to demonstrate that the lncore Monitoring_ Instrumentation ins12.ection of the L-15-139 (JM!} auide tube assemblv soiders. Control Rod Guide Tube a12.12.licable and
Enclosure A L-15-166 Page 4 of 5 Table A-1 Davis-Besse License Renewal Commitments Related LRA Item Implementation Commitment Source Section No./
Number Schedule Comments (CRGTl SQ.acer casting_s1 and additional RV Internals come.anent come.anent items L-15-166 items that ma~ be fabricated from CASS1 martensitic stainless stee/1 or martensitic Q.reciQ.itation-hardened stainless steel materials (e.g_. 1 Core SUQ.Q.Ort Shield (CSSl vent valve toQ. and bottom retaining_
ring_sl will maintain their functionalit~ during_ the Q.eriod of extended OQ.eration. The anal~sis will consider the Q.ossib/e loss of fracture toug_hness in these comQ.onent items due to thermal embrittlement (TEl and/or irradiation embrittlement (!El and ma~ a/so need to consider limitations on accessibilit~ for insQ.ection and the resolution/sensitivit~ of the insQ.ection techniques. The Davis-Besse anal~sis will be consistent with the licensing basis and the need to maintain the functionalit~ of the comQ.onent items being_ evaluated under all licensing basis conditions of OQ.eration.
54 In resQ.onse to MRP-227-A AQ.Q.licant/Licensee Action Item 81 October 221 2016 FENOC A.1.32 ue.date and submit for NRG review and ae.e.rovaf an evaluation for Letters B.2.32 the 12.eriod of extended OQ.eration reg_arding_ the effect of irradiation L-15-139 on the mechanical Q.roQ.erties and deformation limits of the RV and internals that was evaluated for the current term of OQ.eration in L-15-166 AQ.f2.endix E of ToQ.ical ReQ.ort BA W-10008 1 Part 11 Revision 1 SUQ.Q.lemented b~ DB-1 USAR AQ.Q.endix 4A.
Enclosure A L-15-166 Page 5 of 5 Affected LRA Section LRA Page No. Affected Paragraph and Sentence 8.2.32 Page B-129 New 3rd paragraph To address Davis-Besse Reactor Vessel Internals Inspection Plan Action Item 8, LRA Section 8.2.32, "PWR Reactor Vessel Internals Program," previously revised by FENOC letter dated March 9, 2012 (ML12094A383), is revised to include a new third paragraph, as follows:
Locations using replacement bolts. fabricated from Alloy X-750 material. are the upper core barrel (UCB), the lower core barrel (LCB), lower thermal shield (L TS) and surveillance specimen holder tube (SSHT). These replacement bolts have cumulative usage factor analyses that are TLAAs and are managed by the PWR Reactor Vessel Internals Program where volumetric UT examinations are petformed on a periodic basis consistent with the program's inspection plan.