ML19210E651
| ML19210E651 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/30/1979 |
| From: | Dunn C DUQUESNE LIGHT CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| TAC-46826, NUDOCS 7912050465 | |
| Download: ML19210E651 (18) | |
Text
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November 30, 1979 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn: A. Schwencer, Chief Operating Reactors Branch No. 1 Division of Operating Reactors Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Decket No. 50-334 Auxiliary Feedwater/ Containment Pressure Analysis Centlemen:
Enclosed are six (6) copies of the results of an analysis of the response of containment pressure to a steca break accident inside containment with extended auxiliary feedwater flow to the affected steam generator.
This analysis was. performed as a result of questions asked by members of your staff during the month of September, 1979.
The results of this analysis indicate that the postulated event will not result in a containment pressure greater than that for which the structure has been designed.
Very truly yours, 7
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C. N. Dunn Vice President, Operations Enclosures ok s 1497 324 7912050 4C5- t P
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Copies to:
CCRobertson(ene)
BFJones(eno)
EDrotleff(ene)
SBJacobs(enc) ene .
EAWarman(i-(en)e)
TCO'conno **
D 3 LBHiczek(enc) '
BFDodson(ene) ** * ' #
3 Thompson (ene)
SBurke/ job book JCarey(ene)
Mr. Gilbert W. Moore Novenber 7,1979 Duquesne Light Company 435 Sixth Avenue Pittsburgh, PA 15219 J.O. NO.13352.03 DLS 15169 Dear Sirs BEAVER VALLEI POWER STATION - UNIT NO 1 J.O. B0. 13352.03 (JXILIARI FEEDWATER/ CONTAINMENT PfESSURE ANALYSIS This transmittal completes a Stone & Webster analysis effort relative to the effects of a main steamline break (HSLB) on containmant pressure considering unisolated auxiliary feedwater system (AFS) flows for up to thirty (30) minutes after initiation, as requested by the ERC staff in a recent meeting.
At Duquesne's request, S&W attended an NRC meeting on the above subject in Bethesda on 9/21/79. In addition to S&W and Diquesne, VEPCO repre-sentatives were in attendance. As a result of the 9/21/79 meeting, S&W has completed analys is that de:nonstrate the acceptability of the existing BV-1 AFS with respect to a MSLB and the resulting containment pressure transients.
The results of the completed analyses are presented in Attachment 1.
These results ars =4m41=r to the pra14=4 nan results telecopied by S&W to the RRC on 10/1/79 and supplemented by additional infornation concerning analysis parameters on 10/3/79 Both of the telecopied transnittals are includv4 as At+- hment 2. The final results (Attachment 1) show a lower peak containmant pressure than the preliminary results (Attachment 2).
This reduction is due to the elimination of mass and energy blowdown that was added to cent.=in==nt from the two intact steam generators in the pre 14=4n=n analysis.
Attachment 2 also contains the important assumptions used in the analyses.
Attachment 3 presents the more significant plant parameters for BV-1 that might be useful as a basis to judge the applicability of the BV-1 analysis to similar plants. Attachment 4 shows a si=plified sketch of 'the Auxiliary Feedvater system functional arrange =ent.
1497 :25 h
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R The final results shown in Attach.nent 1 demonstrate that the contain= ant design pressure (45 peig) is not azeeeded hy the continued unisolated-AFS flow for more then 30 min. assuming that the affluent discharged to the con +24-t is steam. h analysis also deemnstrates that for the 4 9 ft2 pressures are reached as a result of the initial blowdown. For break,theppbreak,theinitialpeakpressurethatoccurs the 1 4 ft a few minutes after the break occurs is conaida M to be the. limiting peak pressure reached for this accident, however h analysis was continued out to 30 minutes at the request of the ERC staff.
N terminations of the pressure transients shown in Attachment 1 '"#
result from two differert calculational mechanisms. The 4 9 fr,2 break analysis calculates the decrease in heat sources available (heat transfer coefficient assumed constant) until AFS temperature is reached. This resultg in an abrupt decrease of steam flow to W containmant. h 1 4 ft break analysis assumed AFS isolation at 30 min. also resulting in an abrupt decrease in steam flow to the containment.
It areshould be emphasized unrealiatiolly high forthat cont the 1.4=4]ftt break pressures sincepredicted at 30 min.
it was assumed that the availahle energy in the primary system remains nearly constant with time. Therefore, the steam flow to the containment equivalent to the AFS flow rate to the affected steam generator roeults in more staan being generated than the system can provide results in more steam being generated than h system can provide over a 30 min. time period. Based on the analysis evaluation, isolation of the ==414=v feedvater system is not necessary in order to preclude con +24===t overpressurization.
E&W requests DI4 approval to forward Attachment 3 to VEPCO for use as part of their activities related to this same concern for the Surry plants. A comparison of BV-1 and Surry 1 & 2 parameters was requested by MRC at the 9/21/19 meeting attanded by Duquesne and VEPCO.
Following telephone conversation with Mr. J. Carey of Duquesne Light Co.,
B&W has re-evaluated h unisolated feedvater piping volume and the feed-water control valve closure time used in the preitmin=q analysis and the approprintemees of both parameters to Beaver Valley Unit 1. S&W utilisod a feedvater control valve closure time corresponding to greater than the average of the Beaver Valley 1 test results. However, main feed fleva consistent with a depressurized steam generator were assumed.
h s, the mass of main feedvater entering the affected generator has been enveloped in the analysis.
If you have any questions, do not hesitate to call us.
Very truly ,
A D*{D DWhf n.x. Stark w }a Lhpn!]t.
1497 326
ATTAChENT 1 Page 1 of 6 Su: .arv of Final Results of Beaver Vallev 1 Contair. ment Pressure Analvses Initial Time of
. Stea=line P.eactor Peak Initial Pressure S.G. Blowdown Break Power Pressure Peak 3 ISCO see Data ( ft2) M) (PSIG) ( see. ) (PSIG)
Westinghouse 1.4 102 28.4 330 35.3 30 3L.3 650 38.9 0 - -- 41.1 Si',1 - LCCTIC 4.9 102 ( ) 29.9 70 16.2 30 (1) 36.0 75 13.9 0 (1) 36.2 72.5 20.3 0 (2 38.2 73.5 16.3 (1) Initial Cenditiens - 10.4 PSIA, Service Water T = 36 7, Te = 105 0( SAT)
( 2) Initial Conditions - 11. '. PSIA, Service ' dater T = 32 P, Tc = 105 ( SAT)
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ATTACHMENT 2 NOTES CF TELEPHCNE CCNVERSATION Date of Call: October 1, 1979 J.O.No. 13352.03
Subject:
SV-1 MAIN STEAM EREAK ANALYSIS
Participants:
Duquesne Light Co=pany -
Gil Moore Clifford Dunn Jack Carey Nuclear Regulatory Co==ission -
David Wiggenten Janice Kerrigan Elinor Adensam David Stu Stone & Webster Engineering Corp. - '4. C. Drotleff E. A. War An R. M. Stark C. E. Ader F. A. Elia, Jr.
E. A. Thc=as
- 3. F. Jones As requested by the NRC at their meeting, September 21 the status of the 37-1 =ain stea= line break (in the contain=,1979, ent) analysis.
DLC and S&W analysis are attached.Assu=ptions used in the analysis and the preliminary resu of the EV-1 Calculated auxiliary feedvater pu=p run-out flow for the b
ately 1600 gpm, for the two intact loops is approximately 200roken loep is appr coming from the turbine driven pu=p and 550 gpm ce=ing pump. gp: each,frc
900 each gp: met A containment backpressure of 20 psig was included in syste= resistance. erth driven e breken loep auxiliary feedvater pur:p-runout flow, SW stated that 2800 gym characteristics, including calculatedwhereas the 2000 gp= vas based on sabased syste= resistance. more on detailed analysis pu=p be =arked preliminary information,andnot .
tablesfor whichdocketingThe are to N In addition, the NRC asked for a response to theestions: following qu 1.
'Aat =ain feedvater isolation valve closing time waseused in th analysis?
2.
Wat is and generator thethemaximum mainlinesteam nearest main steam line stop valve? volume stes: between the b
~
3.
Wat is the maximum main stes:
generator stop valve and th9 other steam generator stop valves?line 4.
Wat is the total of 2 and 3 above?
)49[} -- -
- 5. khst is the naximum feedvater volume between the r.ain feedwater isolation valve and the steam generator?
- 6. Provide Westinghouse furnished mass / energy release for the 1..' sq ft break for all power levels available.
A copy of S!l:W's responses to the above questions is attached. ':he responses were sent to NRC, attention Elinor Adensam, 301-492-7617, telecopier number 7371, on October 3, 1979. 1497 334
TELECOPIED riur /.M>'
~
CAT" m .// /n.,. 8 Assumptions: -
- = , , ,,
- 1. Main steam non-return valve functions instantaneously to isolate the raulted steam generator break from reverse main steam flow.
- 2. Blowdown rate of the faulted steam genetstor is calculated by S&V/W, feedwater flow control valve goes to full open, zero pressure drop through the steam generator for 30% and 103% cases.
- 3. The two intact steam generators stay pressurized.
- 4. Steam generators are isolated by controls sensing the break.
5 Auxiliary feedvater flow is available within ten seconds, with run-out flow going preferentially to the faulted steam generator per system hydraulics.
- 6. Heat transfer coefficient is constant, heat transfer vs. time per computer code. (~ 1200 BTU /lb)
- 7. Containment backpressure is 20 psig for all cases.
#. 8. Single active failure is one CIB resulting in minimum safeguards; 1.e., failure of one-half of the containment sprays.
9 No operator action is assumed.
- 10. All auxiliary pumps operational.
Footnotes (1 ) . Initial Conditions - 10.4 PSIA, Service Vater T = 86 F, Tc = 105 (SAT) (2). Initial Conditions - 11 c6 PSIA, Service Water T = 32 F, Tc = 105 (SAT) 1497 335 (PRELIMINARY INFCRMATICN - ' NOT FOR DCCKETING)
. J' O.No. /3352. 03 StodE 4 k/EBs72K Answers to NRC Questiens on Preliminary Beaver Valley 1 Containnent Pressure Aralysic
- 1. ht nain feedwater isolation valve closing tine was used in the analysis?
Answer 7.5 sec. 2. ht is the maximum main steam line volume between t' < broken steam generator and the nearest main stean line stop valve? Answer 985 ft 3(Loop A)
- 3. ht is the naximun nain stean line volume between the damaged stean generator stop valve and the other steam generator stop valves?
Answer: 8,0C0 ft 3(O used in the analys'.s)
- 4. ht is the total of 2 and 3 above?
Answer: 8,985 ft 3(985 used in the analysis) 5. ht is the maxinun feedwater volume between the nain feedwa'ar isolation valve and %e steam generator? Answer 283 ft 3
- 6. Provide the Mestingheuse furnished mass and energy release data for the 1./,sq. ft. break for all power levels available.
!'esponse:
Vestinghouse data as inputted to our analysis are given in the at*4ched shee ts. 7~rwccPV TG /MC (ic/3/79) Arreanoa: Euac8 G. ApeasA M Jo/ - y 72 - 76 / 7 x 737/ 1497 336 (FRELIMINARY IN7CRMAT:CN - uCT FCR DOCKETING) ggg g 7- f gp y
PRELIMINARY Summary of Results of B.V. 1 Cont. Pressurs Analyses Initial Time of Steamline Reactor Peak- Initial Pressu~e S.G. Blowdown Power Pressure Peak 8 1800 see Data Breag) (ft (%) (PSIG) (sec.) (PSIG) Westinghouse 1.4 102 I') 33.0 305 38.0 I') 30 39.1 650 42.4 g (1) -- -. 44.1 S&W - LocTIC 4.9 102 I') 34.3 56 32.8 30 C') 41 .8 65 36.5 0 I' ) 42.2 63 36.7 u 31 .2 44.1 63 1497 f.37 ( EELIMINARY Ih?CRMATICU - NCT FCR DCCKETING) .. _
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, PARAMETERS RELATED TO HSLB IN CONTAINMENT 6
2 Break Sizes Considered 4.9, 1 4 ft Steam Generator Inventory ' 0% power 150,000 lb d 1020 psia, 1192 BTU /lb 30% power 136,000 lb @ 929 psia, 1195 BTU /lb 102% power 108,000 lb & 782 psia, 1200 BTU /lb Main Feedwater added to affected Steam Generator 28,836 lb d 416 BTU /lb Hein Steam line backflow to irreak 225d Ib d 1192 BTU /lb AFS runout flow to affected Steam Generator 1594 gpm d 35 paia backpreasure Quench Spray Flow Rate 2030 gpm/ train @ 55 paia containment pressure, full RWST Recirculation Spray Flow Rate 6800 gpm/ train Quench Spray lleat Removal Rate 3.42 X 106 BTU / min / train @ 270 F containment Recirculation Spray IIeat Removal Rate 6.35 X 106 BTU / min / train a 270 F containment, 240 F sump Spray Start Time QS-1 min., RS-5 min. Containment Free Volume 1,800,000 Ft3 BTU's available above 320F 649.8 X 10 BTU (oxcluding decay heat) lleat sinks Surface Area Liner 73,300 ft Steel 156,800 ft22 Concrete 152,400 ft Steel Masa 2.65 x 106 lb n e N u b 6" [ 6a 700 GPM 0 "' ~ BEAVER VALLET-1 RVR
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