ML20024B449
| ML20024B449 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/02/1978 |
| From: | Taylor J BABCOCK & WILCOX CO. |
| To: | Macmillan J BABCOCK & WILCOX CO. |
| References | |
| TASK-03, TASK-07, TASK-3, TASK-7, TASK-GB GPU-0259, GPU-259, NUDOCS 8307080757 | |
| Download: ML20024B449 (5) | |
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TdE B1BCOCK f. WILC0X COMPANY
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, Po%ER G l:E!:t. TIC *! CZCP J. II. mC:4!LLAN. VICE-PRl:SIDENT, NPCD y
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.l". II. TAYi.0!1 - mNAGER. LICENSIM (2317 File no. 205 - T4.4
.l or Ref. PSC 8-77 Cost.
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In June,1977, a safety concern was reported which dealt w!th the The problem relates to water level in some of our 177 OTSCs. acceptable results for the steam line break the fact that accident depend upon a low water inventory and low water level
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it had-at low power levels. Independent of the.5LB accident, been our practice on those plants having seal welded feedwater nossles to keep the water level high until the power exceeded 51 to naintain the nortle fatigue loadings within acceptasle limits.
Actions were The concern was reported on the DB-1 contract.taken to resolve the conc j(
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the water level had to be and technical specificaticas so that lowered before tsking the reactor critical.
Until recently, the evaluation of this conditica had not been now that it has been completed, it appears to completed, but, fall into the cicss of situations which is reportable under
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i Not all of our 177 plants use seal welded nozzlesTM1-1, however, is af fec
.j 10 CFR 21.
and, hence, not all are affected.should be reported as a potential substantial j
tj and we believe itCopies of PSC 3-77 and the evaluation report are j-safety ha:ard.
Licensing has received concurrence of the evaluation Integration.
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,d attached.
from the Manager of Quality Assurance and Plant h
The following subsequent actions are now required:
5 You are requested to indicate the time and date of receipt of this ce::iorandum sad sign on the space provided below; 1.
e1 please return the copy of the signed nemo to me.
J.L the Service / Project Hansger for By copy of this memo Three itile IslanJ Unit 1 is requested.to notify-the 2.
customer of this safety concern snd of the TcPortinglie shou 1J obtain a writte rh
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the NRC has been notified and
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forward same to the Manager, Licensing, tion from the custocer that s
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n9 Charles snapa m m Doyle Reporeg bc.
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If written confirmation of customer notification to NRC is received by tr.tf within 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> of reccipt of this memo e
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by Virc President. NPCD the.stansger, Licensing will notify not (L
tlic NRC of this safety concern.
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Vice-? resident _ QCD Action V
Heno received Signature Tise. Date
.TT:dsf Attachments J. J. Stewart R. P. Williams sn G. M. Olds cc:
A. L. EacKinney D. Mars J. P. Jcues E. R. Kans W. A. Cobb A. H. Lazar
- 3. A. Karrasch E. G. Ward
- 3. 3. Cardwell W. R. Gibson D. "J.
Berger J. T. Janis i
J. C. Desdens Record Center
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g Rcr. ort ca Startup snd Shutdcwn Prscedures For Steam Cenept_ ors tlith.
4 Sent tielded Feedwster_ tot:1es (i O ern involv-This report evaluates the nature of a safety conc 7
in~g startup and shutdont precedures far steam gen h
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T seal velded feedwater nettles.
3, 1977 when it identifisd Just The concern was initia11) ting pracsi.ates and was determined that Dsv$s Jesse 1 opera water ' wye! in tis Teshnical Specificatises differed ca allevad shutiovs condittons.
the steam generators during startup an M-PA plar.t with Further investigation showed that one other Iis operating seal welded feedwater noz:les could Safety Analysis steam generator water level mode ccastrary te fdeat.
assumptions for the steam line hreal aceacz:les,have aa1 with seal we, lied f eedh axr
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The plaats the not!1rs to be I(O startup/ shut!rv:s procedutes t'7at reguire This require =ent is flooded up to 5% of rated thermal power.
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he rozztes ex-imposed to minimize the thets*1 stress that tHowever., this
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perience during hettup aM:
3As safety sna11 sis of the, b
- operatica is inconsistent with thu F
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a steam line 6eak"($13) which sisumes minimun va Therefore, l power.
at zero power and' maximum inventory at ful fl titutes an having a large inventory at est rated power consIt 7
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unanaly:cd situation.
tartup and shutdown, which 4
this situation occurs only during s ing time.
i constitutes a small percentage of totsi operatbrcsk occurring d ri 44j Therefore, the probsbility of a steam lineis significantly less
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this particular moJe of operat on i
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probshility of a stesa line bresk as ana yze.
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I The only Af.W units affected, i.e., with seal velded feedwater O
nml s. ar. D..is 3.sse 1. Thr.. Mile 1 stand 1 ud 2, and Midland 1 and 2.
Howevct, a potential safety concern, which is reportable under 10 CFR 21, exists only at TNI-1.
At E3-1, no salety concern exists sinte 7ecinical Specificatica limits on steam generater water 1svel art cossistent with sat'ety a.sa!ysis 3
4 ass agtf+as. Revised start up proceduros and Technical Kpe.!-
l fications have been satt to D3-1 te pernit floodef feednter noz:les only during subtritical eperatian; these procecurts ensure that the reactor is maintained tubezitical it the event cf s steam line break. It is to *ae petad that TFI-1 Tegar.ical Specificatiocs do not provide a limit os stess generator wate r level as is the esse for Davis Bes.se 1.
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For ntI 2, revised startup/shutdert. procedures have bees O
prepared as described above.!ur Davis 3 esse 1.
Since this plans
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.e is under cosstruction, Technical SpecL!itations and operating i
precedures have not been finali:ed. 1hes prepared, however, t' hey vill be co1sistent wf th the DB 1 resolution.
g For Midl.nd Units 1 and 2, startup/shutdows procedures have nct been prepared since these plants are under construction and
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fuel 1cading is many months in the future. When prepared, 5
operating instructions and Technical specifications will avoid I
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this safety conce.n in a manner analogous to the Davis Besse 1
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resolution.
4 The corrective action required for TMI-1 has been initiated.
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$g Revised startup/ shutdown procedures have been prepared which allow flooded feedwater no::les only during suberitical operations
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Qh. as described above for the DB.1 procedures. The corrective actien y
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for the other affected plants is as described above.
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,ECS is aware of tie cen.
eu st u nts, 1,:t::: May 17, 1!77.
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by TECG Engineering noting a c:nfifct flict b6t not the teplica:fces.
bets.eem Tech Specs and the startup r=dm.
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i.e.. Tit! 1 and 2. Midlano 1 and 2.
[s tstnet..... s 61, se.cs.s. s. fist..rtsn e te..e.t.tt r ). stsitetst as. stir sitis.t.g e t....e s...tv..
soin u eu.:, curis.: Units with seal welded feedwater r.czzles hoe plant startus pro-cedures trat require the r.czzles to be fic:ded (i.e., s 350 in:has above the 1 ewe.-
tausteet) vp to 5: of rated therr.a1 power. ihis is required to minimite the fatigte cycles taat the nczzles cust experience. evever, this retairement cca.flicts with'the' 6
standard Tech Specs which require the levei tc be batheen 13 ed s 35017thes then the n
RCS is > 2C0 F.
.'le idc* nn safety is in the sige, ifne break eralyds. n e F W 1 stater +. hat the
. zero powet :LS is of lesser corsewences t!us car at rated power bm.st tv starti.;
i level is enly 30 inches. The water inventory ans t'ws. the a ou.t of ct:17. 2. m1J *>e greatly lacreased with the *:ezzles flooded. Wi tt: a negat.ve r.:cer.t:- tercerati re i
coefficient, a significant increase in reactivi*y c:uld as producto by a 5'.3.
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condition has not been a1alyttd.
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TMI.1 has operated since the initial startup wit's *Je t.Szzles flooded up ts 5: pcwer.
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ig.iu.ist u.sacties. cree, cueun.iis u..svinse i
A c:eeting was held on f/2/77 to discuss fu*ure actions. See memo. A. F. Mccride to O
Distribution. " Meeting to discuss steam generator Icyc1 during startup/ shutdown 9
precedures.' 5/26/77.
f IVI C h e,.u nt..., Safety Analysis t
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