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Transcript of 850709 Closed Meeting in Oak Harbor,Oh Re Addl Info Request Concerning Serial 517 Ltr & Pump Capacities of Equipment Used to Mitigate Total Loss of Feed. Pp 1-24.Related Documentation Encl
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Issue date:	07/09/1985
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{{#Wiki_filter:(Jo R tO UN11ED STATES NUCLEAR REGULATORY COMMISSION IN THE MATTER OF: DOCKET NO: DAVIS BESSE IllCIDEitT (IliTERVIEW 8 f!EETillG) (CLOSED) Discuss Additional Information Request: Sorial 517 lotterr Flows for AWP, SUFW, !!akeup, llPI, llPI/LPI Piggybacks CWD's O ror as1v s99/ coo. ^re rersiae steem vetve - I r I.OCATION: UAK HARBOR, OH PAGES: 1 - 24 DATE: July 9, 1985 _-_g, ~.~_._,.__._.4>..,.~..s... ,s. ..__,.._,..,,,...m_.,.s. O ace-FEDERAL REPORTERS, INC. OfficfalReporters 4 ;I North Capitol 5treet 0507290200 H50709 Washinaton. D.C. 20001 PDR ADOCK 05000346 C02)347'N T PDft NATIONWICE COVERACE

1-2 Sim 1-1 1 UNITED STATES OF AMERICA 2 NUCLEAR REGULATORY COMMISSION 3 4 I 5 TUESDAY, JULY 9, 1985 6 i 7 8 MEETING BETWEEN Tile NRC PACT-FINDING TEAM AND TOLEDO EDISOM I 9 TO 10 DISCUSS ADDITIONAL INFORMATION REQUEST: jj Serial 517 Lotter l Flows for AFW, SUFW, Makeup, 12 IIPI, IIPI/LPI piggyback 13, CWD's for MSIV's, 599/608 AFP Turbino Steam Valves 14 15 NRC FACT-FINDING MEMBERS PRESENT: 16 ERNEST ROSSI g7 J. T. DEARD LARRY DELL 18 _ TOLEDO EDISON MEMDERS PRESENT: 19 MR. DONNE 20 MR* JAIN MS. MacDONALD 21 22 23 24 Acted.d e,pervers, k 25 m

3 Sim 6-1 1 PROCEEDINGS (11:20 a.m.) MR. ROSSI: We have had a number of loose end kind 2 f qu sti ns that we wanted to discuss with you that we need 3 to know answers to to try to complete our report. 4 One of the.first.ones was a June 15th 1979 letter 5 that went to Mr. Denton from Lowell Roe, and it had a state-6 ment in it to the effect that the ability of the steam 7 g nera r main a n pressure for auxiliary feedwater WMne 8 operation over an extended time has been experienced and 9 w are basically trying to find out what information is there 10 on how long you can run or restart auxiliary feedwater pumps gj with stored steam in the steam generators after they go dry. 12 MR. JAIN: We had another letter that was sent 13 to the NRC on June 23, 1979, Serial No. 522. I only have 94 three copics here of that letter. 15 MR. DEARD: Did you say June 237 16 MR. JAIN: June 23, right. 97 MR. ROSSI; It is a June 23 letter and --- 18 MR. BEARD: Ernie, may I ask that this be entered y9 as an exhibit, whatever the number is. 20 MR. T.OSSI: Yes. That one should go with the 21 transcript. It is a June 23rd, 1979 letter. 22 (The document referred to was 23 marked Exhibit No. 1 and submitted 24 Aor

d p.penm, W, f r the record.)

25 INDEX w.--

4 Sim 6-2 1 MR. JtIN: That describes a scoping calculation, 2 if you will, as to how much steam will be bottled up in 3 the steam generators after they are isolated and how much 4 steam do you really need to start the aux feed pump turbine. 5 What it concludes is that after the isolation 6 you would have about 1600 pounds of dry steam and --, 7 MR. ROSSI: You have about what? 8 MR. JAIN: Sixteen hundred pounds of dry steam and 9 you need about 275 pounds of steam to start the turbine I 10 rolling. 11 MR. ROSSI: Okay. Does this describe any tests 12 that were done at any time? 13 MR. JAIN: It also describes on the second page I 14 believe or at the end of the first page the transient that 15 we had on September 24, 1977 where one generator went dry 16 and I think it went down to 650 psi and the aux feed pump I 17 turbine was started on that steam, generator as it was 18 brought down. 19 MR. ROSSI: So to the best of your knowledge, 20 this has the best information availabic on starting auxiliary 21 feedwater pump turbines with dry steam generators? 4 22 MR. JAIN: To the bent of my knowledge, that is 23 the thing that is on the docket right now to support that 24 kind of operation, j A>f.dere e.por,.ri W. 25 MR. ROSSI: Okay, fino. We will review that. I t

5 Sit 6-3 1 doubt if we will have any questions. We just wanted to be 2 sure that we did indeed have the best information. 3 Do you guys have any questions on that, JT or 4 Larry? 5 MR. DEARD: No. 6 MR. DELL: No. 7 MR. ROSSI: Now the next thing we wanted to get 8 some clarifications on is pump capacities of various 9 equipment that can.be used to mitigate a total loss of 10 feed, and we have some numbers that we have obtained from 11 letters and reports that have boon submitted to the NRC. 12' Maybe the best thing to do is just start with the i 13 various sytems and ask some questions. Picano understand I 14 that what we are interested in are flows and pressures like 15 in the steam generator if we are talking about auxiliary i 16 feedwater pumps and startup pumps and not just head flow 17 curves of the pumps themselves. We are really intercated 18 in their ability and capability to deliver flow during 19 conditions that might exist during the loss of all feed. 20 So that is the kind of thing that we want. 21 Do you have a comment, JT? 22 MR. BEARD: No. You made the point I wanted to 23 bring up. 24 MR. ROSSI: The first one is on the utcam driven A. 7.d.,. n. pori.,i, lac. 25 auxiliary feedwater pumps. The number we have is that the

6 Sim 6-4 I pumps will pump 1050 gpm at 1050 psig in the steam generator, 2 but out of that 1050 gpm it is my understanding that 250 1 3 of it goes for recirculation flow. 4 Now are those numbora correct so that you get.800 5 gpm to the steam generatora from each pump at 1050? i 6 MR. DONNE: That la correct. j 7 MR. BEARD: That is from which pump, the startup 8 ) pump? 9 MR. ROSSI: No. The steam driven auxiliary feed-10 water pump. Il MR. DONNE: At 3600 rpm. I 12 MR. ROSSI: And that in at 1050 psig in the steam 13 generators? i i 14 MR. DONNE: Yes. [

l l

15 MR. ROSSI: Could you tell us, what in the codo 16 safety valvo not point of the lowest on the steam generatorn? 17 NR. DONNE: 1050. 18 MR. ROSSI

Tho code safety valve act point in i

19 1050? 20 MR. DONNE: Right. The Iowant two open at 1050 21 and then they stagger up to 1100. 22 MR. BEARD: How do you have any information ather 23 than just the number or graphical form that you keep? 24 MR. DONNE: Wo have a ronintanco curve that wan ' Aorw.,os n.p.,e... su. 25 generated for un by llechtol. l l

Sim 6-5 I MR. DEARD: On aux feedwater? 2 MR. DONNE: On aux feedwater. This is the curve. j f 3 This is the total flow to both atoam generators. So the 4 flow to each steam generator would be half this. l 5 MR. BEARD: This is actual measured information 6 here? 7 MR. DONNE: No. This in calcualted based upon 8 frictional offects in the piping and stuff like that. 9l i MR. BEARD: So it is calculated based on tents? 10 MR. DONNE: Baned upon the pipo layout --- Il MR. JAIN: And the friction lossen, i 12 MR. DONNE: Right. 13l MR. ROSSI: Now, JT, you have that in front of 14 you. That should go with the tranneript. I 15 MR. HEARD: Yes, and lot me just identify that 16 thoro are two curvos hero. 17 MR. DONNE: Ono in the pump curve and tho other 18 one in tho system runintanco curvo calculated baned upon 19 thu pump curvo. 20 MR DEARD: Wo will put thin in an an oxhibit, 21 whatover the next number in. 22' (The documento rofored to wero l 23' markod Exhibit No. 2 and submitted 24 for the record.) Ao rw.r.: n.p.e.,i, ine. 25 MR. HEARD: Now do you havn any extra copion that

8 4 Sia 6-6 I we could just look at during the meeting or is that the 2 only copy? 3 MR. DONNE: We have a copy here. 4 MR. DEARD: I mean just so we can glanco at it. 5 MR. DONNE: I boliove that is the only copy. i 6 MR. ROSSI: Well, I am more intorested in getting i the information. I don't know that there is any point in 7l 1 81 talking about it unicas somebody has a very specific t 9 question. i i 10 In any event, you are saying that at the safety I 11 valvo not point at 1050 poig that tho aux food pumps will j 12-pump 800 gpm, each one will put in 800 gpm into the steam I 13{ generator and that the other 250 gpm is recirc7 i i I4! MR. DONNE: Right, and that curve should be flowed ) 15 to the steam gonorator. So that curvo does not havo recirc r 16 flow in it. 17 MR. HEARD: Apparently this curvo in for both 18 steam generators an a componito. 19 MR. DONNE: Hight. 20 MR. DCARD: Decouno at 1050 it nhown around 1600. 21 MR. DONNE: Around 1600, you, and that in what j 22 I think the "X" axin labol naya, flow to both atoam 4 l 23 generatorn. Do it is annuming both pumpn. So to got the 24 flow for each utcom gonorator you would just have to havn k w as neewm, w 25 tho air flow and koop the namo ntoam gonorator prennuro. . - ~.

) Sim 6-7 i 1 MR. ROSSI: Now the next question that we had 2 was a similar one on the startup feedwater pump. What is 1 3 its capacity at 1050 psig, which is the steam generator 4 safety valvo set point? 5 MR. DONNE: The only information I was able to 6 find in our files, and I haven't had real time to go in and 7 do a detailed look, was that InW did a report for un, this 8 report on the startup feed pump and the PORV and the makeup 4 9 pumps as to what we would need for a complete loss of l 10 feedwater, of aux feedwater. l 11 MR. ROSSI: Now is that the document that you gavo l 12' us earlier that was a graph? 13 MR. DONNE: It is a June 22nd 1981 document? i 14: HR. ROSSI: Yon, June 22nd, 1981 entitled i 15 " Engineering Summary Heport Of A Complete Losa of Feedwater 16 Transient Analycin For Davin-Denne. " MR. DONNEs, Right. There are three tablen in y7 thero, Tabic 32, 33 and 34, and they give flow vernun 18 back preneure curven for a one-makeup pump operational and y, 20 two makeup pumps operational and a ntartup feed pump p rational. 21 HR. ROUDD Okay. So that han the information for 22 the makeup pumpn --- 23 MR. DONNE: And the ntartup feed pump. Wo are 24 4,. r u,.i s.,.,,., i.e. 25 in the proccan of banically going through to try and reconfirn 1

10 Sim 6-8 1 { those numbers since they were generated back in '81 and no l one downtown is very familiar to all the input that went 3 into those, calculations.- But there was 1omo transmittal of 4 information from us to the B&W about fractional losses in the 5 system. And I believe D&W then probably calculated the system 6 curve. So we are going to try and check these to make sure 7 that those are reasonable. 8 MR. DEARD: Could I ask you a question about the 1 9 report you referred to? 10 ) MR. DONNE: Yes. 11 MR. DEARD: Maybo this in not the right forum, i 12 MR. DONNE: I may not be able to answer it. 13 MR. DEARD: When wo woro given that report, it was 14 marked draf t, et cotera, et cotora, and I guess I am unclear I 15 as to what its status is as far as for within your company 16 l goes. 17 MR. JAIN: Lot mo comment on that, JT. That report 18 por so was never submitted to the NRC on our docket. Ilowever, 19 parts of the results of that report were submitted to the 20 NRC sometime in Juno or July of 1979 after TMI. We had 21 asked D&W to summarizu whatever they had in their filon for 22 I a completo lons of foodwater analysis. So the 1981 report 23 was just a summary, an engincoring summary of all the uf forts 24 Aor.s.,.is.p.n. iu. that they had dono. L 25 At tho time that that won given to Wayno Schiffer, i

11 Sim 6-9 3 two or three weeks ago, there was some confusion in people's 2 minds here as well as B&W as to whether all the things in 3 there were kosher or not. Because of that, we put a note in 4 there is it preliminary. 5 We are doing several other analyses right now, B&W 6 is doing it, which might further validate some or more of those 7 things in there. j g MR. ROSSI: Okay. But the information that we have 9 right now on the consequences of a total loss of feed with i 10 various systems in operation are basically that B&W report, 11 which is apparently the most complete. { 12 There is the EDS report that was done in December 4 13. of 1981. ja MR. JAIN: That doesn't relate to a completc. loss 15 of feedwater analysis. j 16 MR. ROSSI: Well, it has got nomo information in j7 there on the fact that availability of the main feedwater ^ 18 startup pump flow combined with a primary coolant makeup flow 39 for one makeup pump in sufficient to handle. It does have 20 those statements in there and that is formally on the docket i 21 or the dockets. i 22 MR. JAIN: Also you have the June 15, 1979 Ictter. 23 MR. ROSSI: Yes. We have the Juno 15, 1979 letter 24 which basically just gives two of the ploden of information u >r w,. n.p.,,.,.. e,w. 25 that were lator summarized in the ll&W report, and that in m m

f 12 \\ 0 1 basically everything that we think we have got from you on 2 the consequeces of the loss of main feedwater. 3 Is there something else that we ought to know about 4 or be given now? 5 MR. JAIN: Yes. I think thoro is also a volumo 3 6 or the Blue Book, as you call it. I am pretty sure that wan 7 submitted on the docket sometime in May or June of '79, and 8. that essentially talked about -- it didn't talk about startup V makeup PORV, but it talked about how long did you have before 10 you could start aux food pumps. a II MR. BEARD: What do you mean when you refer to tho 12 Blue Book? Can you give me a botter titio? 13 MR. JAIN: Wo call it the Bluo Dook because it wan i 14 blue, but there was an analysin. 15 MR. BELL: That book is referred to in thin letter 16 of Juno the 23rd, right? i 17 MR. JAIN: Correct. That in exactly right. gg MR. BEARD: Could you just road tho titio then? t 39 MR. JAIN: Okay. It nayn Volumo 3 of the Evaluation i 20 of Trannient Behavior arid small Roactor Coolant Cyntum tirunka 21 in the 177 ruel Annombly Plant. 22 MR. ROSSI: I bo11cvo wo have that, too. But my 23 recollection of that in that it didn't havo no much information 24 'n it au tho othur thron reportn. Ao r 4., s e.p.n.,. w. 25 MR. JAIN: Correct. m

13 MR. ROSSI: I mean it didn't have anything really Sim 6-11 1 mr that added to the other reports. 2 l MR. JAIN: That in true. 3 MR. ROSSI: Okay. So we have got the best informatior-4 n the makeup pumps, and this is the primary coolant makeup 5 pumps, for one pump and for two pumps. 6 Wo have got your boat information on the startup 7 pump, and those come out of the D&W report. Wo have that, 8 t MR. DONNE: We have that. 9 MR. ROSSI: And we havo now verified what wo under-10 stood about the aux feed pump flow and pronsure. Now the high preneuro injection pumpu, the nafety related high 12 pronsure injection pumps, we havo for thoso that they havo a 13 94 ! shutoff head without being piggybacked of 1630 puig, that that is basically the shutoff hoad when they aru not piggybacked, l 15 l, 16 and when they are piggybacked, they are 1930 poig. 4 MR. D011110: That in about correct. Dechtol went 97 back and did a nyntom ronistanco curvo for thu llPI back in jg 39 May of 1979, and they did it for both linon uning the tunted 20 pump curvon for both pumpn. Thorn is nomo ulight difforencu i in the tonted charactorintien of the hund curvo for tho two 21 22 IIP! pumpn that wore tented. Tho 1630 in tho ono with tho 23 1 wont lumd, which in high prennuro injection pump flo. 1. l HR. Itorin t : llow much highor in tho other onu? 24 A a r a e,a nopersen, w 25 Mit. DOtitil:: IL lookn liko it in about 'io to 60 pn1 r

15 i Sim 6-13 I system. For 1000 gpm using the decay heat system, which la 2 I think 8 or 10-inch piping, the frictional effects were t 3 probably very minimal. 4 MR. BELL: 11ut that suction piping f rom the LPI 5 pump dischargo to the IIPI nunction would have to -- you would 6 have to take into account the frictional offect of air. 7 MR. DONNE: Wo banically said t. hat would be a wanh 8 between the auction piping whero the IIP 1 normally taken of f 9 to the pump ountion, and thone would be comparablo. 10 MR. DELL: Of oqual value, i 11 MR. DONNC: You. 12, MR. DEARD: 80 what you aru paying in, if I 3 13 understand you correctly, and lot mo mako ouro that I do, l 14 this in your company's boat outimato to dato. i 15 Mit. DON!1U Yon. 16 MR. B!: Alm can you junt road the numborn of i 17 the shutoff headn7 18 MH. DONNE: Okay. Por pump No. 1, for llPI injection 19 it nhown around 16 --- l 20 MR. !)CADD: No. I moan for piggyhack. 21 MR. DONNM Okay. 1830. 22 MR. H0001: That in for tho lowont head pump? 23 MR. DONN!:: Tho lowont head pump, yon. Tho nocond 24 pump whoro wo have a ulightly highor lipI nhutotf hond, tho sor,4e3 n pusen, se,. 25 piggyback goon up to around 1990. Tho uhutorf hond in

16

Sim 6-14 1

piggyback would be around 1890. 2 MR. ROSSI* Are you people fairly familiar with 3 the feed and biced modo of operation? , MR. DEARD: ilait junt a second, Ernie. Can wo 4 3 got this entered as an exhibit. 6 (The Pump _ Flow charts referred I y to woro marked Exhibit No. 3 i 8 and submitted for the record.) i l XXXXXXXXX-9 l end Sim 10 l Joo foin i ~ 11 12 13 l 14 r 15 16 17 l 18 l 19 to 21 22 23 24 i u. tw.# s.r.,...., au-25

14 higher. So it is a combination of probably the frictional Sim 6-12 1 2 effects of those differences in the pump curves. 3 MR. BEARD: So what did your curve indicate the 4 shutoff point for the other curve was? 5 MR. JAIN: 1708. 6 MR. DONNE

It was 1700.

7 MR. DEARD: 17087 8: MR. DONNE: Right. 9 MR. ROSSI: I gather that you have curves that wo 10 can put in our transcript? I I !, MR. DONNE: Yes. 12 MR. ROSSI: Ilow about for piggyback operation, do i 13{ they have nimilar information for piggyback operation? i 14 MR. DONNE: They didn't have it, but yesterday IS l we went in and basically superinposed upon the IIPI pump the 16 head developed by the decay heat pumps. And over the O to 17 1000 gpm programs, the head developed at the decay heat pumps 18 is pretty flat. So it is basically a constant Delta P, and. 19 we superimposed that Delta P on the llPI curves that nechtel 20 generated. 23 MR. ROSSI: And those are all with system frictional 22 lansen and no forth also? 23 MR. DONNH Por the decay heat we didn't go in and 24 include any decay heat in the LPI portion of the piping. So Ao %.i sep.,,,,,, iae. 25 the fractional effects would be whatever was in the llPI i

1 17 7-1-Wal, J. 1 MR. ROSSI: Let's see. Do you have anything 2 clso that we ought to have. We are going to proba bly try 3 to do calculations within the NRC. 4 I don' t know how quickly they are going to get 5 done, but there are a number of ef forts underway to calculate 6 feed and biced and that kind of thing within the NRC to see 7 what the consequences are. 8 Is there any other information that you have 9 that would be useful in that effort that we haven't thought 10 of? 11 MR. DONNE: Well, the only -- we have B&W 12 basically going through and doing similar type calculations 13 now. Right now they are analyzing the 6/9 ovent. 14 Eventually they may be made -- tell them to 15 go ahead and just do a hundred percent power case. They 1-6 haven't started that yet, but they are basically prepared i 17 to do that. 18 We don't have any of the results back from the { 19 6/9 ovent yet, but we expect them some time this week. 20 Preliminary results from B&W. 21 The only thing that we discovered in talking to 22 them that may affect the analysis, and B&W has talked to Bob 23 Jones at the NRC about this, and he is aware of it, is that 24 the PORV capacity is actually graded on the old graded Ace Federal Repo,ters, Inc. 25 capacity based upon the EPRI test results. L

18 7-2-W31, J. 1 EPRI tested the PORV -- they tested the North 2 Anna PORV, just a small bore diameter, and it ran for around 3 2500 psia. They were measuring steam blow down around 150 4 to 160 thousand pounds. 5 With our larger bore diameter, our estimate is 6 at around 2,500 psia we should be able to pass around 200,000 7 pounds, and that number is being used by B&W in their analysis 8 and it has been passed to Bob Jones at NRC. 9 That's only other thing that I am aware of that 10 may af fect any feed and biced analysis upon them. 11 MR. ROSSI : What is the code safety valve set 12 point on the parameter side? 13 MR. DONNE: It is 2,500 psig -- 14 MR. ROSSI: 2,500 psig. 15 MR. DONNE: That is right. 16 MR. BEARD: The PORV set point I believe is 17 2425. 18 MR. DONNE: 2,400. 19 MR. JAIN: We could verify that. 20 MR. BEARD: The numbers we were given earlier, 21 if I remember them correctly, was 2425 to open, 2375 to 22 close. 23 MR. DONNE: Sounds good. 24 MR. BEARD: So that the discharge would be a w r m.,e n. porters,inc. 25 little bit greater than that number.

i ~7-3-Wal, J. 19 1 MR. DONNE: The discharge would be a little 12 bit lower. What they were doing is they were using that 3 to calculate the flow area. 4 MR. BELL : These other documents that you have 5 showed us concerning a loss of feed water event address the 6 startup pump and the makeup-pump. 7 .However, your procedure directs the operators 8 to enter the-PORV cooling mode using makeup pumps and the 9 high pressure injection pumps, and we asked for analyses that 10 showed the flows, and whether or not that mode of cooling 11 would be adequate. 12 Is that the analysis that B&W is working' on, 13 or do you have -- 14 MR. DONNE: The B&W analysis has the -- is 15 assuming that the HPI would be put in piggyback at 30 minutes 16 into the eventi 17 Now, depending upon what the system pressure 18 is, it would depend upon whether we can get.any benefit out 19 of it. ~ 20 MR. ROSSI: I would think that that would do _ you 21 no good if you got it at'30 minutes. I'mean.even from --'- 4 22 MR. DONNE:- That was our feeling that it doesn' t-23 really matter because we are not going to get -down to 'that 24 pressure fast enough really to get any benefit.out of. it._ . Am-Federal Reporters, Inc. 25

i 20 7-4-Wnl,'J. hj .1 MR., BELL: Until and if the high pressure 2 injection pumps -- excuse me, the makeup pumps -- turn 3 temps. 4 MR. DONNE:- Right. Turn the pressure down 3 when they catch up to decay heat and start depressuring 6 and eventually on the way down we would pick up the piggy-7 back -- HPI in pippyback. 8 The analysis they are doing, we don' t really 9 expect to see piggyback come into play until, for all 10 practical purposes, the transient is over. 11 MR. ROSSI: Okay. We had a question of what 12 was done with the makeup flow,- flow control valve,- during 13 the event. 14 Do. you people know the answer to that, or is 15 that going to be somebody else? 16 MR. JI.IN: I would rather defer. that. 17 MR.-ROSSI: You want to defer-tha:t. 18 MR. HELLE: Can I ask a question about the 19 procedures? Do-the procedures address the makeup flow 20 control valve? If I go to Section 6-on overheating -- 21 -MR.'JAIN: I know what you are talking about. 22 I am not too sure what exactly it tells him to do. 23 MR. BEARD: The reason I am curious is that '24 that and' piggyback are:both some place _in the_ procedures. But Asem nesorim. Inc. -25 I ~didn' t find anything, if I remember corre ctly, that -in t-

~.7-5-Wal, J. 21 ' y 1 Section 6 itself brings that up. 2 And so it would be somewhat contingent upon 3 the operator tying this all together, so to speak. If you 4 follow what I~am trying to say. 5 MR. JAIN: Yes, I exactly follow you. 6 1m. BELL: You are saying Ohat he has to-tie 7 together specific rules 1. and 2 in Section 6, which directs 8 him' to initiate those modes of cooling for those specific 9 coolants? 10 MR. BEARD: I know that specific Rule 2 deals 11 with piggyback. It basically says except for one exception 12 he is allowed to piggyback.whenever he wants to, and 13 specific rule -- I don't know which one it is, talks about 14 the makeup valve as one of the four or five subparts. And 15 I am trying.to understand whether the operator really could 16 b e expected to tie that little facet with this, and come up 17 with exactly the best combination for a"particular event. 18 And it is not obvious that he would.. 19 MR. JAIN: May I suggest that we have the 29 person who wrote the procedure here who could answer that. 21 MR. BEARD: That is fine. 22 MR. ROSSI: Okay. I am looking -- I think we 23 have covered -- the serial 517. letter, I. guess, is :this ~24 question on turbine driven auxiliary feedwater., We have - neperms, sac. 25 covered.that. . e have covered the flows. Let me ask you a W I

7-6-Wal, J _ 22 1 :. 'l question. 2 g The flows that you are giving us, does Bob Jones 3 have those, do you-know? 4 MR. JAIN: lie has been talking to Bert Dunn, 5 who is the ECCS person. 6 MR. DONNE: I~believe he has makeup flows and 7 the startup' feed pump flows. 8 MR. ROSSI: Okay, fine. So, those will be going 4 9 into the calculations. j 10 MR. DONNE: IIe has been, like Sushil said, been 1 II talking to Bert Dunn at B&W, and I believe Bert has passed J 12 that information on. 13 MR. ROSSI: Okay. Then the next item on the t 14 agenda was the drawings for the MSIVs, 599 608 and the 15 auxiliary feed pump turbine steam valves, ~ j. 16 MR. BEARD: Could I ask an administrative ~ 17 question? On the agenda that you folks ' prepared here, it i 4 { 18 says.CWDs. What does that stand for? i 19 MR. JAIN: Control wiring' diagrams. 1 20 MR. BEARD:.Are those the drawings that you 21 gave me earlier? 22 MR. JAIN: Yes. 23 .MR.. BEARD: Okay. So,'I think'we ought to just 24 acknowledge that we received them, and obviously have not-4 -F.esens napoems. lac. 25 reviewed them yet, and we will: discuss them later. 1 l -e-.-.e,wy ei. ,y +w- ,m,-u,*+-,em- .g-,-~<,-- r w

7-7-Wal, J. 23 j MR. ROSSI: Okay. Then, are we to a point now 2 where ve want to close this meeting, and we will reconvene 3 when you two fellows have reviewed each others things? 4 Did you have anything else that you wanted to 5 bring up? 6 MR. DONNE: No. 7 MR. JAIN: I thought you were suggesting to me 8 this af ternoon on the action plans for the SFRCS? 9 MR. ROSSI: Righ t. We can discuss it at that jo time. f i 11 MR. BEARD : And I think we were going to do i i 12 both of them jointly. { l 13 MR. ROSSI: Okay. Then why don' t we adjourn for i 14 now, and we will reconvene at 1:00 for the afternoon session., 15 (Off the record discussion ensues.) 16 MR. ROSSI: We are back on the record because j7 there has been some questions raised about the trouble i 18 shooting action plan on steam and feedwater rupture control { i 19 system trip /MSIV closure, and we would just like to clarify i 20 that yesterday the NRC had -- we received this plan over the 21 weekend, and we did review it and felt that there was no need ' 22 to hold any further meetings on it. 23 So, we want to clarify that that plan is, as far 24 as we are concerned, they are ready to proceed with it. They Anrea:3 nwonm. w. I 25 can proceed with it, and the meeting this afternoon is only

7-8-Wal, J. 24 1 2 going N cover the operation of the steam and feedwater rupture 3 contro'.e nystem. 1 4 The remaining questions that we want to talk 5 about -af ter people have looked at drawings and sketches that -6 have been interchanged this morning. 7 Okay. We will reconvene at 1:00 p.m. ~ s 9 (Whereupon, the meeting concluded at 12:02 p.m., i 10 this same day.) i . gj ? 12 I 13 4 4 4 I 15 16 i - 17 18 J 19 i j .20 i 21 j. 22 23 24 Ac F.e s si por,.r. fine. 25 l s e -.,ei y ~ _~~1, -m m..

'9 $ M B o r 99L/ ih B5 ./ -- a / TOLEDD Files: 0017; 0028 LDWELL E. RDE Docket No. 50-346 S a * ".,'.... m e. , c. License No. NPF-3 Serial No. 522 June 23, 1979 Director of Nuclear Reactor Regulation Attention: Mr. Robert N. Reid, Chief I'$ Operating Reactors Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Co= ission - Washington, D.C. 20555 l!u

Dear Mr. Reid:

This letter transmits the following information requested by G. R. Mazetis:

1) An analysis on the capability of a dry and isolated steam generator to start an auxiliary feedwater pu=p 30 minutes

(- after the loss of all main and auxiliary feedwater.

2) 'Ihe test results for anticipatory reactor trip syste=.

Yours very truly, f s) W w/ Attach. 1 LER:FRM BCC: P. M. S= art, Esq.,w/o Attachent G. Charnoff, Esq., w/ Attach. I D. H. Hauser, Esq., w/o W. A. Johnson, w/o

4. D. Murray, w/ Attach.1 J. G. Evans, w/ Attach. 1 J. S. Grant /R. P. Crouse, w/o J. D. Lenardson, w/o C. T. Daft, w/o gJ. Myers, w/ Attach. 1 E. C. Novak, w/ Attach. 1 C. R. Doz::eck, w/o W.

C'. Rowles, w/o R. Rosenthal, w/o J. R. W er, w/ M. Malcon, w/o A. Smart, Det. Edison,w/ A. H. La % w/o B&U Owners Group, w/ R. E. Lapp, w/o CNRB Members, w/ C. M. Rice, w/o W. E. Nyer, w/o THE TDLEDD ED'SDN COMDAPW ED:SDN PLAZA 300 MAD SON AVENUE TDLEDO. 04:0 43tS2

Docket N. 50-346 / Lic:ns] No. EPF-3 ./ Serial No. 522 Attachecnt I June 23, 1979 r Ouestion 1 Discuss the ability of the secondary system to support AFW steam turbine operaticn at 20 minutes af ter loss of feedwater to the generator. Resoense Davis-Eesse Nuclear Power Station Unit 1 (DS-1) is designed to redundantly isolate each stea= generator (50) upon initiation of SFRCS. The steam generators are not cross-connected on either the 12ed or steam system side when isolated. In any loss of feedwater condition, SFRCS isolates the steam generators and starts the auxiliary feedwater (AFW) steam turbines to provide auxiliary feedwater flow to the generatern within 40 secends. If for some reason one or both redundant safety grade AFW trains do not initiate for thirty cinutes there will be adequate pressure to start the pu=ps. This is illustrated by both calculation and experience at DB-1. .The sequence of events would be as follows: a) LOFW b) Reactor trip c) STRCS - isolated steam generators (assume no AFW initiation) d) Decay heat removal due to primary to secondary heat transfer to steam generator inventory, boiling off the inventory to atmosphere via main g7 steam safety valves. Secondary system pressure 1050 psig c=550 F. e) As soon as the generator inventory boils off from a reactor trip at any previous power level, decay heat removal to that generator is lost. If both generators are dry, all decay heat is removed via the boil-off of the primary syste= through the PORV, pressurizer code safety valves and/or break. This has been analyzed in Volume III of the " Evaluation of Transient Behavior and Small Reactor Coolant System Breaks in the 177 Fuel Assembly Plant", dated May 16, 1979. This will let pressure f all to main steam safety resent setpoint and isolate all dry steam loss fro: the steam generator. With this total SG isolation the steam genera-tor should be at approximately 1000 psig and will remain pressurized indefinitely. During this time, the dry superheated steam in the steam generators will be at primary system te=perature and there will be no heat transfer through the steam generator. There will be 3412 Cu.Ft. (c=1600 lb.) of dry superheated steam in the 50 at 1000 psig available to start the AFW pumps. At a full rated flow, the AFW turbine conserva-tively requires 33,000 lb./hr. steam flow. The turbine starts in 30 seconds after steam inlet valves start to open which =eans that it will require about 275 lbs. of steam to start and bring -the AFW pump up to full speed at full rated flow against full steam generator pressure. As a bounding argu=ent to this case, D3-1 has had one event in which a steam generator did not receive AFW when actuated on September 24, 1977.

p n. _..- ~ ' 5 l' a .[ Docket No. 50-346 License No. h7F-3 Serial No. 522 June 23, 1979 During this event one AFW pump was running at 2600 rpm while the SG was dry.' During this condition the SG pressure reduced to about 650 psig in 16 minutes. At that time the operator manually increased the AW pu=p speed and the SG pressure imediately increased, due to the introduction of AW to the SG. Additional details are found in the Supplement to the September 24, 1977 Licensee Event Report dated November 14, 1977. 9 q 4 9 0 4 4 t I t

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= S Q. ' (.)' ) C ABINET I C ABINET 2 CHANNEL CHANNEL CHANNEL CHANNEL' i 3 2 4 BUFFER SUFFER BUFFER UUFFER bit 7t LOGIC LOGIC LOGIC LOGIC BUFFER BUFFER GUFFER BUFFER 6 N 877 RELAY R E L AY RELAY R E L AY 7 A C TU ATION ACTUATION ACTU ATION A'C T U ATIO N .-e s.:. - 2: tb

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Table 1: SFRCS EQUIPMENT ACTUATION f (SWEET 10F 2)$HAwet. $ Mw t $ g '- A ertur o d (:u e. :. nwJ Steam Line 1 SG Low /High Level Low Pressure Reverse FW to SG dP Loss of Four (Over-Riding Action) Steam Line 2 Low Press RCPs Only Check Closed: Chec1k Closed: Check Closed: ICS-11B AVV #1 ICS-118 AVV #1 AG-3869 AFP #1 Disch to SG #2 MS-101-1 MSIV BYPASS #1 MS-101-1 MSIV BYPASS #1

MS-106A

2 MS to AFPT #1 MS-394 MS ORAIN #1 MS-394 MS DRAIN #1 Check Open:

MS-611 SG DRAIN #1 SP-78 SU FW CONT VLV #1 SP-78 SU FW CONT VLV #1 MS-106

1 MS to AFPT #1 MS-106
1 MS to AFPT #1 AF-3870 AFP #1 DISCH to MS-101 MSIV #1 SG #1 MS-100 MSIV #2 AF-3870 AFP #1 DISCH to AF-3869 AFP #1 DISCH to SG #2 Steam Line Low Pressure SG #1 SG Low /High Level Reverse FW to SG dP FW-780 NFW BLK VLV #1 FW-780 MFW BLK VLV #1 SP-6A MFW BLK VL'/ #2 SP-6A MFW CONT VLV #2 Check Closed:

AF-608 AFV #1 DISCH to ICS-118 AVV #1 SG #1 MS-101-1 MSIV BYPASS #1 MS-394 MS DRAIN #1 AF-3869 AFP #1 DISCH to MS-611 SG DRAIN #1 SG #2 Check Open: Check Open: MS-106A #2 MS to AFPT #1 MS-106

1 MS to AFPT #1 AF-3869 AFP #1 DISCH to SG #2 AF-3870 AFP #1 DISCH to SG #1 AF-608 AFW #1 DISCH to SG #1 CHECK TRIPPED:

CHECK TRIPPED: Main Turbine Main Turbine R actor (via ARTS) Reactor (via ARTS) 07/05/85 5.6-4 DAVIS BESSE INCIDENT SEC 5.6

Table 1: AFRCS EQUIPMENT ACTUATION (SHEET 2 0F 2) ACTUATION CHANNEL 2 FULL TRIPS Steam Line 1 SG Low /High Level Low Pressure Reverse FW to SG dP Loss of Four (Over-Riding Action) Steam Line 2 Low Press RCPs Only Chick Closed: Checlk Closed: Check Closed: ICS-11A AVV #2 ICS-11A AVV #2 AF-3871 AFP #2 OISCH TO SG #1 MS-100-1 MSIV BYPASS #2 MS-100-1 MSIV BYPASS #2

MS-107A

1 MS to AFPT #2 MS-375 MS DRAIN #2 MS-375 MS DRAIN #2 Check Open:

MS-603 SG Orain #2 P-7A SU FW CONT VLV #2 SP-7a SU FW CONT VLV #2 AF-599 AFP #2 DISCH to SG #2 FW-601 MFW STOP VLV #2 FW-601 MFW STOP VLV #2 MS-107

2 MS to AFPT #2

MS-107A #1 MS to AFPT #2 MS-107

2 MS to AFPT #2 AF-3872 AFP #2 DISCH to SG #2 MS-101 MSIV #1 MS-101 MSIV #1 MS-100 MSIV #2 MS-100 MSIV #2 Half Trip AF-3872 AFP #2 DISCH to AF-3871 AFP #2 DISCH to SG #1 Steam Line Low Pressure SG #2 SG Low /High Level Reverse FW to SG dP FW-779 MFW BLK VLV #1 FW-779 MFW CONT VLV #2 Check Closed:

SP-6B MFW CONT VLV #1 SP-6B MFW CONT VLV #1 ICS-11A AVV #2 MS-100-1 MSIV BYPASS #2 Check Open: Check Open: MS-375 MS ORAIN #2 MS-107A #1 MS to AFPT #2 MS-107

2 MS to AFPT #2 MS-603 SG DRAIN #2 AF-3871 AFP #2 DISCH #1 AF-3872 AFP #2 DISCH to SG #2 AF-599 AFW #2 DISCH to SG #2

If open at the time of the trip, valve must be manually closed.

Check Tripped: Check Tripped: Main Turbine Main Turbine ACTOR (via ARTS) REACTOR (via ARTS) l 07/05/85 5.6-5 OAVIS BESSE INCIDENT SEC 5.6

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CERTIFICATE OF OFFICIAL REPORTER This is to certify that the attached proceedings before the UNITED STNTES NUCLEAR REGULATORY COMMISSION in the matter of: NAME OF PROCEEDING: DAVIS DESSE INCIDENT (Interview & Meeting) (CLOSED) DOCKET NO.: PLACE: OAK IIARBOR, Oli DATE: TUESDAY, JULY 9, 1985 were held as herein appears, and that this is the original transcript thereof for the file of the United States Nuclear Regulatory Commission.

M

' [ r, ( sig t). '7)._, " r" /,/.[/j/b/b/ (si t (Typed) MY,dTLE II. WALSil ^ ^b "' Of'ficial Reporter ACE Federal Reporters Official Reporter Reporter's Affiliation ACE Federal Reporters _ sigt) M% ( (Typed) MARY 6d10NS Of ficial Reporter i ACE Federal Reporter .}}

ML20129B886

Text

Dear Mr. Reid:

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