ML19220B984
| ML19220B984 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane  |
| Issue date: | 11/30/1976 |
| From: | Zwetzig G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904280032 | |
| Download: ML19220B984 (4) | |
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NUCLEAR REGULATORY COMMisslON f 3 pfk-d j WASHINGTcN, D. C,2C555 Novemcer 30,19/c o,
DOCKETS fiOS.: 50- 269/ 270/ 287/ 289/ 302/ 312/ 313/ 320/ 3 a6 VENCOR:
BABCCCK & WILCOX COMPANY (B&W)
FACILITIES:
OCCNEE 1, 2, AtiD 3 RANCHO SECO-1 ARKANSAS NUCLEAR ONE-1 THREE MILE ISLAND 1 AND 2 DAVIS-BESSE 1 CRYSTAL RIVER -3 SL'MMARY OF MEETING HELD ON NOVEMBER 3,1976, TO DISCUSS B&W'S PRCPOSED REACTOR VESSEL INTEGRATE] SURVEILLANCE PROGRAM On November 3,1976, representatives of B&W arJ scme of the ownc s of B&W reactors met with the staff to discuss several mat *.ers reieted to surveillance of B&W reactor vessels f r:.tuding a possibic 7%j, sed Surveillance Program for reactor vessel materials. A list 01 attendeed is attached.
Holder Tube Status The first topic discussed was the status Of the redesigned Surveillance Specimen Holder Tubes (SSHT's). B&W reported that redesigned SSHT's had been installed at Davis-Besse 1 and Trystal River 3.
The acceptability of the new design is iWng tested during the Hot Functional Test currently uncerway at Davis-Besse 1.
Reports describing the new design and the instrumentation to be used during the tests at Davis-Besse i have been submitted to the NRC for review. B&W plans to request a meeting with the staff to discuss the results obtained from the Davis-Besse 1 tests as soon as the results are available.
Integrated Reactor Vessel Surveillance Procram The next topic discussed was a contemplated Integrated Reactor Vessel Surveillance Prcgram (IRVSP) for B&W 177 fuel assembly reactors.
B&W representatives stated that the IRVSP would be discussed in a generic sense only and asked that the record reflect that no utilities have yet comitted to the program.
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Meeting Summary #cr November 3, 1976 As background for the program, B&W reported the projected times at which the vessels at the various B&W plants would reach an upper shelf energy of 50 ft-los.
In many cases it appeared that this limit would be reached well tefore the end of reactor life.
Per 10CFR50, Appendix G, Paragraph V.C., when this limit is reacned, additi nal measures are required to assure continued reactor vessel integrity. One of these misures is the perfor,ance of a fracture analysis for the vessel in question. B&W noted that because only limited experimental data are currently available for use in such an analysis one of the objectives of the IRVSP was to include specimens which would be useful in developing additional experimental data. B&W also described how the data could be used in fracture mechanics analyses.
B&W next reported that information developed over the past year on the effects of copper and phosphorus impurities on weld sensitivity leads them to the conclusion that all limitir.g welds in B&W vessels are not represented in the current sets of sur-veillance specimens. Accordingly their plan for an IRVSP also includes provisions for replacing some of the carrent specimens which do not represent limiting welds with specimeis which do.
J Staff questioning clarified the fact that the IRVSP being discussed by B&W at this meeting differed frcm the IRVSP's previously requested by Arkansas-1 and Rancho Secc.
- n those requests there was no sub-stantial change in the makeup of the surveillance specimen sets from those initially installed in these reactors.
B&W described three testing a?ternatives they were considering to Avelop additional fracture toughness data:
1.
Research oriented capsules in the reactor vessel surveillance program.
2.
Test reactor irradiation program.
3.
Ccmbination of test reactor and operating reactor irradiation.
B&W then described the composition of the capsules that would be employed, how the capsules would be utilized in an Integrated Reactor Vessel Surveillance Program for the various testing alternatives, the schedule by which data would be available, and the advantages and disadvantages of each testing option. The description also addressed how B&W's definition of the necded exposure data could be obtairec without exposing any specimens in Crystal River 3 during its #irst operating cycle.
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.n ! bider T., Irealiation EN.i d2? crib <i the proce.'ur's which vmid be follcued in innt lling r2desicred SSHT's in irradiat2J re:::,rs.
This :culd invc!ve rareval of all fuel frem tha reactor to th2 Econt fu:1 ster:ge rcol and rer'r/al of the core su~ crt stru::urc 0 n the vessel to th: internals storace stand in tt;e icel tr:n:far canal. '!tilizina Water chicidir, t::a holder tub 2s v.c.uld then :2 instciled um'ar-
\\;2 tar u:ir.; ica;-M i !c.'. spccially asico:i t:01: c'erstc' fece platforms anc brid'.eu a!.ava tr.e water shieldina.
0."' aise describ2' 50.2 c f tM p r bi c.,: inv21vad in tt: installation, such 3 drillics and t370in: blind hole; in the core ba r:1, :hir.in" to ob! in
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They also 2.orntrea their v.a i that all o e :ed irradiction data c;uld be catair.c;d l rcr 3 '!! plar,1.e about the :.artuo so th t there v:s r.c r.22d to install t.;e holcers in irradiate plc.nts.
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tated that the following action ua: needed:
1.
Dr.C per..it creratien of Crystal River-3 during fir:t cycle withe.t sur.cillance s;ccirens.
2.
MRC aporove integrate-! surv2illan:2 progr:r at Cavis-C:-s:2. T"I-2 and Crystal River-3.
3.
U.?.C indicata licensinc usefuir.es of scacican irradiatico data frca test rsactors.
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B'!,l to wly additienal in c~ :tica en rec:n :i integra:c': curveil-lance pre rea en a ceneric i, asis until cu:n ir.fer.mtien 1: reend on a specific Ccckat.
U"J.! will also senad.ile a conting aith th
!!RC in tha naar futur'2 on the subhet of cutron fluence credictic't.
The t:ff cdvised B*l-l tr.at iter.: 1 and 2 uera currently under active review and t'a: item 3 would Le studied.
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MEETING WITH B&W NOVEMBER 3, 1976 B&W ACRS W. J. Keyworth E. G. Igne L. H. Bohn C. D. Thompson Consumers Power Company A. L. Lowe, Jr.
A. F. Eckert A. John Birkle E. O. Hooker C. E. Barksdale Arkansas Power & Licht R. R. Steinke K. E. Suhrke Donald A. Rueter
- 0. H. Roy Garry G. Young Cuke Power _
R. O. Sharpe Meted J. J. Moran Florida Power Cqro.
J. Alberdi J. T. Rodgers NRC D. K. Davis G. B. Zwetzig W. E. Converse R. P. Snaider D. Neighbors R. Reid R. Klecker P. ;iandall V. Noonan J. R. 1:awthorne P. A. Kiefer J. E. Ouzts J. A. Dyer K. G. Hoge 84-L. Shao W. Hazelton
g MEETING SUMvARY DISTRIBUTICN ORB #4
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Docket File (g)
LShao CNeighbors NRC POR (9)
RBaer RKlecker L POR (g WButler PRandall ORB #4 Rdg)
BGrimes VNconan NRR Ffg Project Manager JHawthorne BRusche Attorney, OELD PKeifer ECase OI&E (5)
J0uzts VStello RIngram JDyer KGoller RFraley, ACRS (16)
KHoge DEisenhut TBAbernathy WHazelton TCarter
.1RBuchanan ASchwe'icer DThompson, E/W 359 DZiemann NRC Participant (s)
GLear RReid DKDavis RSnaider aR 84 712