ML18113A648

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Forwards Responses to NRC Questions Re Permanent Solution of Low Head Safety Injection & Spray Pump Net Positive Suction Head Problems in Response to 780131 NRC Ltr Requesting Addl Info
ML18113A648
Person / Time
Site: Surry  
Issue date: 11/22/1978
From: Stallings C
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Schwencer A
Office of Nuclear Reactor Regulation
References
NUDOCS 7811300222
Download: ML18113A648 (34)


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIRGINIA 23261 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:

Mr. Albert Schwencer, Chief Operating Reactors Branch 1 U.S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Denton:

November 22,. l978 Serial No. 069C/013178 PO/DLB:scj Docket Nos.

50-280 50-281 License Nos.

DPR-32 DPR-37 This is in response to your letter of January 31, 1978 which requested additional information on the permanent solution of the low head safety injection and outside recirculation spray pump net positive suction head problems, and is a supplement to our previous submittals of March 16, 1978, April 14, 1978, and April 28, 1978.

Responses to questions 2.0, 3.0, 5.0, 6.0, 7.0, 10.0 and 11.0 are attached. You should now have responses to all questions included in your January 31, 1978 request.

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Response to Questions 2.0, 3.0, ;.o, 6.o, 7.0, 10.0, and 11.0

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f Question 2.0 Provide a table of the values of the containment second peak pressure and the third peak pressure for the spectrum of break areas.

Response

Table 2.0-1 presents the containment second peak and third peak pressures for a 1.0, 0.6, and 0.3 pump suction guillotine rupture with minimum ESF.

The initial conditions that maximize the second peak pressure (containment integrity assumptions) were assumed because the difference between the third peak pressures of the second peak pressure analysis and the third peak pressure analysis is small. The analysis is based on the input evaluation parameters presented in Table 3 of Reference 2.~l.

Reference 2.0-1 NPSH Report - Surry-1 & 2, attached to letter to Mr. Edson G. Case, Acting Director of Nuclear Reactor Regulation, U.S. NRC from Mr. C. M. Stallings, Vice President - Power Supply and Production Operations, VEPCO, dated November 22, 1977.

TABLE 2.0-1 Containment second and third peak pressures for a spectrum of pump suction guillotine ruptures vith minimum ESF J

PS Break Area 1.0 DER 0.6 DER 0.3 DER Second Peak Pressure psig 44.2 44.2 43.4 Third Peak Pressure psig

-0.27

-0.27

-0.29

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Question.3.0 For the case which results in the maximum containment second pealc pressure and for the case which results in the maximum containment third pealc pres-sure, provide the following information:

Question 3.1 A discussion of the conservatism in the heat transfer correlations used to calculate the heat transfer from the. containment atmosphere to the passive heat sinks and vice versa:

Response

See response in prior information submittal of April 1978.

Question 3.2 A graphic presentation of the heat transfer coefficient as a function time:

Response

See Figure.3.2-1 Question 3.3 A graphic presentation of the containment atmosphere pressure as a function of time:

-*=*--*-** __

Response

See Figure 3.3-1 Question 3.4 A table of mass and energy release rates as functions of time:

Response

See Table 3.4-1 Question J.5 A table of mass and energy rates of ECCS spillage as functions of time:

Response

See Table 3.4-1

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Question*3.6 A graphic comparison of the mass and energy release rates used for calculating the containment pressure response with the mas~ and energy release rates as predicted by Westinghouse for the Surry plants:

Response

See Figures 3.6-1 and 3.6-2 Question 3.7 An energy inventory for the folloving energy sources and sinks initially, at the end of blovdown, at the end of reflood, at the time of containment second peak pressure, at the time vhen the primary system pressure and the containment pressure are at equilibrium, at the time when the containment pressure returns to zero psig and at the time of containment third peak pressure (all energy inventories should be referenced to 320F). Specifi-cally, provide lists of:

3.7.l The energy stored in the:

(a) reactor core (b) reactor coolant system metal (c) reactor coolant, and (d) steam generator fluid and associated metal 3.7.2 The energy from:

(a) core decay heat (b) accumulator tanks (c) containment spray, and (d)

ECCS injection water 3.7.3 The energy in the containment atmosphere vapor and air, and the energy absorbed by containment structures:

3.7.4 The energy removed by the:

(a) recirculation spray heat removal coolers (b)

ECCS injection water, and (c) containment spray water

Response

The energy inventory is presented in Table 3.7-1 for the following times:

Event Time, sec Initially End of Blowdown Primary= pontainment Pressure End of Reflood Second Peak Pressure Containment Pressure= 0 psig Third Peak 0

17.5 17.5 202.

202.

2600.

5200.

  • -*** ----~------------**-*..... ----------*----* ------------**---... **-**-.... ---*-** --------------** **-*- *-.

The energy inventories are referenced to 32°r. It should be noted that after end of reflood (202 sec), the energy stored in the reactor core, reactor coolant system metal, reactor coolant, and steam generator fluid and associated metal and the energy from decay heat and ECCS injection water is reflected in the*INPUT BLO'WDOWN and SPILLAGE.

Question 3.8 The justifications and assumptions made regarding the time at which the refueling water storage tank empties.

Response

See response in prior information submittal of April 1978.

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  • TABLE.3.4-1 CONTAINMENT INTEGRITY ANALYSIS PSDER WITH MINIMUM F.SF tlASS AtfD EHERGY RELEASE RATES, SPILLAGE RATES, AtfD INTEGRATED RELEASES AHO SPILLAGE I

NOTEt RATE DATA IS CONSTAHT OVER THE TIHE IHTERVAL AHO IS EQUAL TO THE CHANGE IN THE c--

  • IHTEGRATED DATA OVER THE TIIIE INTERVAL DIVIDED BY THE DURATION OF THE IHTERVAL ti

RATE DATA-------------------------------


IHTEGRATED DATA----------------------

--TUIE INTERVAL---


BLOHDOHN--------


SPILLAGE--------. --TIHE--


BLOl'IOOHN--------


SPILLAGE--------

--START-- ---EtfD--

---HASS---

--ENERGY--

---HASS---

--ENERGY--

---HASS---

--ENERGY--

---MASS---

--ENERGY--

(SEC)

(SEC) lLBII/SECI (BTU/SEC)

(LBWSECI lBTU/SECI (SEC)

ILBHI IBTUI ILBIIJ CBTUI f1' o.o 0.1 l.292JE+05 7.4379Et07 o.o 0.0 0.1 l.292JE+Oll 7.4'379E+OcS o.o 0.0 0.1 1.0 5.7352E+04 J.2901E+07 o.o o.o 1.0 cS.4539E+04 3.7049E+07 0.0 0.0

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1.0 2.0 5.5086E+04 J.1660E+07 o.o o.o 2.0. l.1962E+OS cS.6909E+07 0.0 o.o 2.0 3.0 5.J577E+04 J.1156E+07 o.o o.o J.O l.7320E+05 l.0006E+08 0.0 o.o 3.0 4.0 S.1751E+04 3.0142E+07 o.o 0.0 4.0 2.2495E+05 l.J021E+08 o.o o.o IJ.O 5.0 IJ.9785E+04 2.8929E+07 0.0 0.0 s.o 2.7474E+05 l.5914E+08 o.o o.o s.o cS.o IJ.7472E+OIJ 2.7564E+07 o.o o.o cS.O 3.2221E+05 l.6670E+08 o.o o.o 6.0 7.0 IJ.2817E+OIJ 2.4907E+07 o.o o.o 7.0 3.650JE+OS*

2.1161E+06 0.0 0.0 7.0 8.0 l.OllOE+OIJ l.0604E+07 o.o o.o 8.0 3.7511JE+05 2.2221E+06 o.o 0.0 8.0 9.0 S.IJ775E+OJ cS.597cSE+OcS o.o o.o 9.0.J.60cSlE+OS 2.2861E+08 o.o o.o 9.0 10.0 J.2765E+03 J.9537E+06 o.o 0.0 10.0 3.8J89E+05 2.J276E+08 o.o o.o 10.0 11.0 l.9407E+Ol 2.JJ50E+06 0.0 o.o 11.0 J.6583E+OS 2.J510E+08 o.o o.o

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11.0 12.0 l.2575E+OJ l.5095E+06 o.o 0.0 12.0 J.8709E+OS 2.J661E+08 o.o o.o 12.0 13.0 9.3225E+02 l.1167Et06 o.o o.o 13.0 J.8802E+05 2.3772E+08 0.0 0.0 13.0 111.0 7.22J7E+02 8.cSJ94E+OS 11.0 0.0 14.0 J.6874E+05 2.J859E+08 o.o o.o

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111.0 15.0 5.6562E+02 6.9955E+05 0.0 0.0 15.0 J.89JJE+05 2.3929E+08 0.0 o.o 15.0 16.0 IJ.9212E+02 5.8766Et05 o.o 0.0 16.0 3.8962E+05 2.3967Et06 0.0 0.0 16.0 17.0 3.49llE+02 IJ.164JE+05 o.o o.o 17.0 J.9017E+05 2.4029E+08 0.0 0.0 17.0 18.0 2.0494E+02 2.7070E+05 5.2282E+Ol IJ.ZlOSE+OJ.

18.0 3.9038E+05 2.IJ056E+08 5.2262E+Ol IJ.2105E+03 18.0 19.0 S.4362E+02 7.3136E+05 2.06cSlE+OJ l.6715E+OS,

19.0 3.9092Et05 2.4129E+08

2. ll8'1E+OJ l,71JcSE+05 19.0 20.0 3.1325E+02 IJ.169cSE+05
  • 2.4695E+03
1. 9863Et05,

20.0 J,9123E+05 2,4171E+08 4,cS279E+03 3,cS999E+OS 20.0 21.0 3,2031E+02 IJ,2cSSJE+05 l.J797E+03

1. 0982Et05
  • 21.0 J.915SE+05 2.4214E+08 6.007SE+03 4.7981E+05 21,0 22.0 3,6687E+02 4.6602E+05 2.1932E+02 l.7400Et04.

22.0 3.9192Et05 2.4262E+08 6.2269E+OJ 4.9721E+05

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22.0 23.0 J.5262E+02 IJ.cS469E+05 o.o 0.0 23.0 3.9227E+05 Z.4309E+08 cS.2269Et03 4.9721E+05 23,0 24.0 J.6144E+02 4.7432E+05 Z.8661E+03 2.2602E+05.

24.0 J.9263E+05 Z.IJ356E+08 9.09JOE+OJ 7.232JE+05 Z4.0 25.0 IJ.8912E+02 6.J771E+05 5.5660E+03 4.4092E+05, 25.0 J.9312E+05 2.4420E+08 l.4679E+04 l.l642E+06 25.0 26.0 4.965cSE+02 6.438cSE+05 5.4634E+OJ 4.3104Et05 26.0 3.9362E+05 2.4485E+08 2.0l42E+04 l.5952Et06 I

26.0 n.o IJ.9925Et02 6.468SE+05 5.3706Et0l 4.2316Et05.

27.0 J.9412Et05 2.4549E+08 2.5513Et04 2.0184E+06 I

27.0 28.0 5.0112E+02 cS.4909E+05 S.2096E+OJ IJ.l009Et05 28.0 l.9462E+OS 2.4614E+08 3.072JE+04 2.4264E+06

!ft 28.0 29.0 S.OcSJ7E+02 cS.556JE+OS IJ.941JE+OJ J.6975Et05, 29.0 3.9513E+05 Z.4680Et08 J.5664E+04 2.8182E+06 I

29.0 JO.O 5.lll9E+02 cS.cS179E+05 4.7569E+OJ J. 7306Et05

  • 30.0 3.9561fE+05 2.4746E+08 4.0421E+04 3.1913Et06 30.0 35.0 5.0501E+02 6.5268E+05 4.9064Et03 J.5719E+05.

35.0 J.98lcSE+05 2.5072Et08 6.495JE+OIJ

.IJ.9772E+OcS 35.0 40.0 IJ.96llfEt02 6.:S890Et05 IJ.3529E+03 J.1398E+05.

40.0 4.0064Et05 2.5392E+06 8.6718E+04 6.5471E+06 40.0 45.0 4.8639Et02 6.2519Et05 2.4737E+Ol ' Z.4662Et0:S, 45.0 4.0308E+OS 2.5704E+08 8.68/JlEtOIJ 6.5594E+06 45.0 50.0 4.7551E+OZ 6.1055E+05 4.4175E+Ol 4.1318E+OJ, 50,0 4.0545E+05 2.6010E+06 8.7062E+04 cS.5801E+OcS 1 of 2 QI I

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  • I TABLE 3.4-1 (cont)

CONTAINMENT INTEGRITY ANALYSIS PSDER WITH MINIMUM ESF A.

HASS AND ENERGY RELEASE RATES, SPILLAGE RATES, AND INTEGRATED RELEASES AND SPILLAGE NOTE:

RATE DATA IS CONSTANT OVER THE TIME INTERVAL AND IS EQUAL TO THE CHANGE IN THE

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INTEGRATED DATA OVER THE TIME INTERVAL DIVIDED BY THE DURATION OF THE INTERVAL


*---------------RATE DATA-------------------------------


INTEGRATED DATA----------------------

A

--TIME INTERVAL---


BLOHDOHN--------


SPILLAGE-------- * --TIME--


BLOHDOHN--------


SPILLAGE--------

--START-- ---END--

---HASS---

--EtlERGY--

---HASS---

--ENERGY--

---MASS---

--ENERGY--

---IIASS---

--ENERGY--

(SEC)

(SEC)

(LBH/SEC)

I BTU/SEC)

ILBII/SECJ CBTU/SEC)

CSEC)

CLBtl)

CBTU)

CLBII)

(BTU) ft 50.0 55.0 4.6JOOE+02 5.9J91E+05 6.5912E+Ol 5.81J76E+Ol.

55.0 4.0777E+05 2.6J07E+08 8.7J92E+OIJ 6.609JE+06

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55.0 60.0 4.4937E+02 5.7586E+OS 4.2275E+Ol 3.6212E+OJ 60.0 4.1002E+05 2.6594E+08 8.760JE+04 6.627SE+06 60.0 72.5 4.3269E+02 5.5316E+05 2.4830E+Ol l.9474E+03 72.5 4.1542E+05 2.7266E+06 8.79111E+OIJ 6.6516E+06 72.5 85.0 4.1083E+02 S.2365E+05 l.9820E+Ol l.4599E+03.

85.0 4.2056E+05 2.7940E+08 8.8161Et04 6.6700E+06 85.0 105.0 3.9309E+02 4.9916E+05 1.2775E+Ol 8.9290E+02 105.0 4.2842E+05' 2.8939E+08 8.6417E+04 6.6879E+06 105.0 140.0 J.7052E+02 4.6741E+05 8.839JE+OO S.2694E+02 llJO.O 4.4139E+05 J.0575E+06 8.8726E+OIJ 6.7063E+06 140.0 190.0 3.327SE+02 4.1562E+05. 8.8740E+Ol 4.SIJ96E+OJ 190.0 4.580JE+05 J.2653E+08 9.Jl63E+04 6.93J6E+06 190.0 240.0 2.J091JE+02 2.8904E+OS 2.8084E+02 S.171J7E+04.

240.0 4.6957E+OS J.4096E+08 l.0721E+OS 9.5212E+06 240.0 290.0 2.0594E+02 2.5272E+OS J.Jl09E+02 6.5928E+04.

290.0 4,7987E+OS J.5362E+08 l.2376E+05 l.2818E+07 290.0 400.0 l.6J17E+02 l.91J51E+OS 3.7368E+02 7.5577E+04.

400.0 4.9782E+OS J.7501E+08 l.6469E+OS 2.1131E+07

  • I 400.0 525.0 l.0524E+02 1.2510E+OS 4.3185E+02 9.0998E+04.

525.0 5.1098E+05 3.9065E+08 2.1887E+05 3.2506E+07 f

525.0 700.0 9.6JSJE+Ol l.1371E+OS 4.4079E+02 9.0932E+04 700.0 5.2764E+OS 4.105SE+08 2.9601E+OS 4.8419E+07 700.0 950.0 8.9250E+Ol l.0468E+05 4.4796E+02 8.8SJOE+04.

950.0 5.5015E+OS 4.3672E+08 4.0800E+OS 7.0SS1E+07 950.0 1200.0 8.3570E+Ol 9.9166E+04 4.5370E+02 8.6006E+04.

1200.0 5.7104E+OS 4.6151E+08 5.2142E+05 9.2053E+07 1200.0 1450.0 7.4876E+Ol 8.7438E+04 4.6244E+02 l.6114E+04 1450.0 5.8976E+OS 4.8337E+08 6.3703E+05 9.6081E+07 1450.0 1700.0 6.7631E+Ol 7.8592E+04 4.697JE+02 6.6730E+OJ 1700.0 6.0667E+OS 5.0JOZE+08 7.5447E+05 9.7750E+07 1700.0 1950.0 6.2172E+Ol 7.2067E+04 4.7522E+02 6.7509E+OJ.

1950.0 6.2221E+OS 5.210JE+08 8.7J27E+05 9.9437E+07

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1950.0 2200.0 S.7185E+Ol 6.6130E+04 4.802JE+02 6.8222E+OJ.

2200.0.6. 3651E+05 5.3757E+08 9.9J3JE+OS l.0114E+08 2200.0 2450.0 5.2395E+Ol 6.0460E+04 4.8501E+02 6.6904E+03 2450.0 6.4961E+OS 5.5266E+08 l.1146E+06 l.0287E+06 9

2450.0 2700.0 4.7945E+Ol S.5228E+04 4.8944E+02 6.9SJ6E+03 2700.0 6.6159E+OS S.6649E+08 l.2369E+06 l.0460E+08 2700.0 2950.0 4.4070E+Ol 5.0692E+04 4.9331E+02 7.0068E+Ol 2950.0 6.7261E+05 5.7916E+08 l.J60JE+06 l.06J6E+08

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2950.0 3200.0 4.0805E+Ol 4.68811E+04 4.9656E+02 7.0554E+OJ

  • 3200.0 6.8281E+05 s;9oaaE+oa l.4844E+06
1. 0812E+08 3200.0 3450.0 J.8526E+Ol 4.42J2E+OI&

4.90JlE+02 l.2862E+04

  • 3450.0 6.9244E+05 6.0194E+08 l.6070E+06 l.1134E+06 3450.0 3700.0 3.901J2E+Ol 4.4608E+04 4.2728E+02 S.2407E+04 3700.0 7.0220E+05 6.1314E+08 l.7138E+06 l.2444E+08 a

3700.0 3950.0 J.6499E+Ol 4.1688E+04 4.3006E+02 S.2064E+04.

3950.0 7.11JJE+05 6.2J62E+08 l.8213E+06 l.3745E+08 tit 3950.0 4200.0 3.4788E+Ol 3.9964E+04 4.Jl90E+02 S.1911E+04 4200.0 7.ZOOJE+OS 6.JJ61E+08 l.929JE+06 l.5043E+08 I.

4200.0 4qso.o 3.46J4E+Ol 3.9807E+OIJ 4.J211E+02 5.l780E+OIJ.

4450.0 7.2666E+05 6.4356E+08 2.0J7JE+06 l.63J8E+08 4450.0 4700.0 3.4191E+Ol J.9J09E+04 q.J257E+02 5.1765E+04.*

4700.0 7.372JE+05 6.SJ39E+08 2.1455E+06 l.76J2E+08 f:

4700.0 4950.0 3.l661JE+Ol l.8707E+04 4.3312E+02 5.1796E+OIJ 4950.0 7.4565E+OS 6.6306E+08 2.* 2537E+06 l.8927E+08 4950.0 5200.0 3.J241E+Ol 3.8221E+OIJ 4.JJ54E+02 5.1824E+04.

5200.0 7.5J96E+05 6.7262E+08 2.J621E+06 2.0222E+08

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TABLE J.7-1 CONTAINMENT INTEGRITY ANALYSIS PSDER WITH MINIMUM ESF

,111111\\ *

  • LOCTIC ENERGY DISTRIBUTION OIILLIONS OF BTU 1S)

TltlE=

O.OSEC 17.5SEC 202.0SEC 2600.0SEC 5200.0SEC A

HEAT SOURCES PRIIIARY COOLANT 221.96 28.61 13.18 ll.18 13.18 PRitlARY HOT tlETAL PIPING,PUIIPS, VALVES 24.58 24.48 23.82 23.82 23.62 REACTOR VESSEL+ INTERNALS 61.64 60.26 54.07 54.07 54.07 PRESSURIZER tlETAL + LINES 13.69 13.. 02 12.95 12.95 12.95 STEAII GENERATOR tlETAL 112.58 111. 34 99.60 99.60 99.60 STEAi! GENERATOR SECONDARY HATER 154.69 160.59 116.97 116.97 116.97 PRESSURIZER HATER 24.31 o.o 0.0 0.0 0.0 CORE SENSIBLE HEAT 25.61 10.94 4.62 4.62 4.62 EXTERNAL HATER STORAGE TANHIS) 39.60 39.60 36.25 28.0lf 22.lf6 ACCUNULATOR CONTENTS ll.60 6.53 0.01 o.oo 0.00 I.

HEAT SINKS CONTAINHEHT ATIIOSPHERE HATER 5.89 168.28 210.90 25.90 19.53 CONTAINIIENT ATtlOSPHERE AIR l.llf 3.05 3.25

1. 76 1.60 CONTAINHENT FLOOR HATER 0.0 42.40 82.16 390.66 424.90 CONCRETE SINHS o.o 4.!)9 25.06 76.51 71f,52 CONTAINIIENT LINER + HETAL SINHS o.o 9.47 38.38 J0.37 19.49 r

HEAT INPUTS INPUT BLOHDOHN IHERC) o.o 0.0 0.0 230.18 Jlfl.69 INPUT SPILLAGE UIERC) 0.0 0.0 0.0 96.89 195.21 DELAYED FISSIONS o,o 2.91 2.95 2.95 2.95 DECAY HEAT 0.0 2.56 21.86 21.66

£1.86 ZIRCONIUtl-HATER REACTION o.o o.o o.o o.o 0.0

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FEEDHATER o.o o.o 0.0 0.0 0.0 PUIIP ANO FAN HEAT o.o 0.0 0.13 1.36 2.55 TURBINE PLANT STEAtl INVENTORY o.o o.o o.o o.o o.o H E A T OUTPUTS LHSI & HHSI SUHP SUCTION !HERC) 0.0 o.o

1.

o.o O*.O 99.81 RECIRCULATION COOLERS 0.0 o.o 1\\

0.88 174.14 276.07 CONTAINMENT AIR COOLERS o.o 0.0

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o.o o.o 0.0 HEAT LOST TO ATMOSPHERE 0.0 0.0 0.0 o.o o.o ff, STEAi! GENERATOR DUMP 0.0 o.o

\\I 0.0 o.o o.o STEAtl GENERATOR RELIEF VALVE o.o o.o i:

o.o 0.0 o.o (ii.;

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FIGURE 3.i2-1 CONDENSINO COEFFICIENT CONTAINMENT INTEGRITY LOCA HIN EIF

  • l'IIDl!lt. TIC=DIS P IUIIY I AND t 1290118 o'

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rf TIME AFTER LOCA (SECONDS)

FIGURE 3. 3-11 PRESSURE TRANSIENT CONTAJNHENT INTEGRITY LOCA KIN ra,. ra0t1.,x.. as, IUllY I AMO I StaOSI

0 0 CD 0

0

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FJ0.3.6-1B HASS RELEASE RATES COHPARI60N CONTAINHENT INTEGRITY ANALYSIS 0 LOCTIC CALCULATED KATES A. NfSTINOHDUSE CRLCULRTfD RRTfS

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Question*5.0 For the break which results in the lowest available NPSH, provide an energy inventory for the following energy sources and sinks initially, at the end of blowdo-wn, at the end of reflood, at the time of containment peak pressure, or at the time when the primary system pressure and con-.

tainment pressure are in equilibrium, and -at the time when the containment pressure returns to zero psig (all energy inventories should be referenced to 32°F).

5.1 The energy stored in:

(a) the reactor core (b) the reactor coolant system.metal I ( c) the reactor coolant, and (d) the steam generator fluid and associated metal 5.2 The energy from:

(a) core decay heat (b) accumulator tanks (c) containment spray, and (d)

ECCS ~njection water 5.3 The energy in the containment atmosphere vapor and air; and the energy absorbed by containment structures; and 5.4 The energy removed by the:

Response

(a) recirculation spray heat removal coolers (b)

ECCS injection water; and (c) containment spray water The energy inventories for the limiting cases for recirculation spray and low head safety injection pumps are presented in Tables 5.0-1 and 5.0-2, respectively,for the following times:

Event Initially End of Blow.own End of Reflood Peak Containment Pressure Primary= Containment Pressure Containment Pressure= o*psig RS Pump Time, sec

o.
16.

NA 10 16 545 LHSI Pump Time, sec

o.

17.8 204 204 17.8 1950

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'I The energy inventories are referenced to 320F. It shou1d be noted only for the LHSI NPSH analysis that after end of reflood (204 sec), the energy stored in the reactor core, reactor coolant system metal, reactor coolant, and steam generator fluid and associated metal and the energy from decay heat and ECCS injection va.ter is renected in the INPUT BLOWDOWN and SPILLAGE

  • I G

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TABLE 5.0-1 RECIRCULATION SPRAY PUMP NPSH ANALYSIS HLDER WITH NORMAL ESF LOCTIC ENERGY DISTRIBUTION CHILLIONS OF BTU'SI l

  • TitlE=

O.OSEC 10.0SEC 16.0SEC 5lJS.OSEC 1200.0SEC HEAT SOURCES

/

22.ss

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PRIHARY COOLANT 221.96 26.25 25.39 20.30 i

PRitlARY HOT tlETAL I

  • PIPING,PUIIPS,VALVES 24.58 24.51 24.49
14. 71 10.31 REACTOR VESSEL+ INTERNALS 61.64 61.33 60.36 45.95 35.84 PRESSURIZER tlETAL + LINES 13.69 13.42 13.07 12.77 12.40 STEAH GENERATOR HETAL 112.58 112.58 112.56 112.58 112.58 STEAM GENERATOR SECONDARY HATER 154.69 159.30 159.30 159.30 159.30 PRESSURIZER HATER 24.31 1.13 0.25 o.o 0.0 CORE SENSIBLE HEAT 25.61 14.90 12.03 3.87 3.11
  • EXTERNAL HATER STORAGE TANKISI 39.80 39.80 39.80
31. 78 20.78 ACCUHULATOR CONTENTS 13.60 12.62 9.07 o.oo o.oo HEAT S I N I( S CONTAINtlENT ATHOSPHERE HATER 9.06 185.57 186.26 22.68 1.19 CONTAitlllENT ATMOSPHERE AIR 1.11 3.53 2.98 1.64 0.28 CONTAitlHENT FLOOR HATER o.o 49.43 49.90 196.02 187.88 CONCRETE SJ;NHS 0.0 2.23 3.94
29. 71 27.93 CONTAINMENT LINER+ HETAL SINKS o.o 4.27 8.58 28.39 17.83 HEAT INPUTS INPUT BLOHDOHN UIERC I o.o o.o o.o o.o o.o INPUT SPILLAGE (tlERCI o.o 0.0 o.o o.o o.o DELAYED FISSIONS o.o 3.12 4.01 4.24 4.24 DECAY HEAT o.o 1.46 2.29 48.10 88.73 ZIRCONiln-1-HATER REACTION o.o o.o o.o o.o 0.0 FEEDHATER 0.0 o.o 0.0 o.o o.o PUHP AND FAN HEAT o.o o.o o.o 0.99 2.51 8

TURBIHE PLANT STEAH INVENTORY o.o o.o 0.0 o.o o.o HEAT OUTPUTS LHSI & HHSI SUHP SUCTION IHERCI 0.0 o.o o.o o.o 0.0 RECIRCULATION COOLERS o.o o.o o.o 70,89 188.29 CONTAIHIIENT AIR COOLERS o.o o.o o.o o.o o.o HEAT LOST TO ATMOSPHERE o.o o.o o.o o.o 0.0

~

STEAM GENERATOR DUIIP o.o o.o o.o o.o 0.0 STEMI GENERATOR RELIEF VALVE 0.0 o.o o.o o.o o.o

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TABLE 5.0-2 LOW HEAD SAFETY INJECTION PUMP NPSH ANALYSIS PSDER WITH MINIMUM F.SF LOCTIC ENERGY DISTRIBUTION (MILLIONS OF BTU 1S)

TIHE=

O.OSEC 17.8SEC 204.0SEC 1950.0SEC 5700.0SEC HEAT S O U R C E S PRIHARY COOLANT 221.96 12.70 13.06 13.06 13.06 I

PRIHARY HOT HETAL 0

PIPING,PUMPS,VALVES 24.58 24.48 23.79 2'3.79 23.79 REACTOR VESSEL+ INTERNALS 61.64 60.22 53.87 53.87 53.87 PRESSURIZER HETAL + LINES 13.69 13.02 12.95 12.95 12.95 STEAH GENERATOR METAL 112.58 111.34 99.55 99,55 99.55

~

STEAH GENERATOR SECONDARY HATER 154.69 160.58 116.83 116.63 116.83 e

PRESSURIZER HATER 24.31 o.o o.o o.o o.o CORE SENSIBLE HEAT 25.61 10.81 4.52 4.52 4.52 CXTERNAL HATER STORAGE TANHCS) 39.80 39.80 38.0l 30.12 19.81 ACCUHULATOR CONTENTS 13.60 8,37 0.01 0.00 o.oo HEAT SI ti HS CONTAINHENT ATHOSPHERE HATER 9.06 183.54 189.43 22.00 10.27 CONTAINMENT ATHOSPHERE AIR 1.11 2.97 3.09 1.63 1.22 CONTAINMENT FLOOR HATER o.o 66.45 110.55 393.39 U6.35 CONCRETE SINHS o.o 4.23 21f.60 67.17 58.66 e

CONTAINMENT LINER+ HETAL SINHS o.o 9.56 36.42 30.86 13.06 HEAT INPUTS INPUT BLOHDOHN (HERC) o.o o.o o.o 293.86 609.03 e

INPUT SPILLAGE OIERC) 0.0 o.o 0.0 o.o 0.0 DELAYED FISSIONS o.o 2,92 2.95 2.95 2,95 DECAY HEAT o.o 2.60 22.04 22.04 22.04 ZIRCONIUH-HATER REACTION o.o o.o o.o o.o o.o FEEDHATER o.o o.o O.*O o.o o.o PUMP AND FAN HEAT o.o o.o 0.14 1.03 2.79 TURBINE PLANT STEAM INVENTORY o.o o.o o.o o.o o.o H ! AT OUTPUTS LHSI*& HHSI SUHP SUCTION (HERC) o.o o.o o.o

  • 0.0 154.61 RECIRCULATION COOLERS o.o o.o 0.75 152.59 320.75 CONTAINMENT AIR COOLERS o.o o.o o.o o.o 0.0 HEAT LOST TO ATHOSPHERE o.o o.o o.o o.o o.o STEAH GENERATOR DUMP o.o o.o o.o o.o o.o STEAH GENERATOR RELIEF VALVE o.o 0.0 o.o o.o o.o
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,I Question*6.o Graphically, compare the mass and energy release rates used for NPSH analysis vith the mass and energy release rates as predicted by Westinghouse for the Surry plants.

Response

See Figures 6.0-1, -2, -3, and -4.

0 0

CD 0

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TIME. C SECONDS J FJG.e.0-2B ENERGY RELEASE cnnPARlamt LIHITING RS,unP.NPSH ANALYSIS 0 UCTIC ca.cuumD M1U 6 MOTi~ ca.cu&.:rm IIIITEI

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,10.a.O-SA nA88 RELEASE ~ATES CONPRftJSDN LINITINO LHSI PUNP NPSH RNRLY8I6 A O LCCTIC Clil.CUUIT!D ltfll'!I NnTIN8ffOUK CIIU:UUfmJ MTEI

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,10.e.o-se NR81 REL[R8t RATEi CONPARt8BN LJHJTJNO LH81 PUHP NPSH RMALY8I8

. 0 LOCTIC CILCUUITtl MID 6 N!ITIN&ftOUK CM.CUUITtD atn

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ENERGY RELEASE RATES CBTU/SEC)

X10 -*

500 1000 1600 2000 2600 3000 3500 4000 4500

---.------,...--.-:-*--:~*---=-~.... ~-~-------,...... ----~-----~-.. -_... __..... _..:..-.*----*~-=----=.. -~ *-*-.:.~-----*:-:-.**

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cf TIME CSECONOSJ FIG.8.0-49 ENERGY RELEA8! CONPARISGN LINITING LH8I PUNP NP8H ANALY8J8 o ucnc cacuunm a10

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  • Question*7.0 Graphically, show the pump suction friction head, static head, and total dynamic head as functions of time for the inside and outside RS and I.HSI pumps *.

Response

See Figure 7.0-1.

e -

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F.IGURE 7.0-1 STATIC, SUCTION FRICTION, & TOTAL DilUMIC HE.AD TRANSIENTS. ~

,+)

fo-4 *-'i G) =

+J fo-4 -*

'i G) =

12 10 8

6 4

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12

-10 s

6 4

14 12

  • ~ 10 fo 4 r,

0

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0

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200 400 600 Time (sec) 800 ORS PUMP HI.DER WI TH NORM ESF S'l' A'.r IC I

SUCT.rON RRICTION I

2CO

400 600 800 Time (sec)
  • LHSI PUMP PSDER 'WITH MIN ESF I

STAfl=IC i

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SUC7'ION IF.RIC" rl:ON I

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.:,000

- 3400 3800 4200 Time (sec)

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.&.JJ,l I

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5000

~--~----~-----*----------------------------*-----

r-..

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400

/

200 200 400 300 200 5400

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Question.*10.0 Provide, on one curve, the containment depressurization for the worst case LOCA under the present containment spray configuration and the proposed spray configuration. Describe in detail the effect of the introduction of chilled spray water as proposed on ECCS performance.*

Response

See Figure 10.0-1. The transients are based on initial conditions that maximize the second peak pressure. In addition, the evaluation input parameters presented in Table 3 of Reference 10.0-1 and Reference 10.0-2 were used for the present and proposed spray configurations, respectively.

The effect of the introduction of chilled spray water on ECCS performance will be discussed separately in a later response.

References 10.0-1 VEPCO Response to NRC Order of August 24, 1977, attached to letter to Mr. Edson G. Case, Acting Director, Nuclear Reactor Regulation, U.S. NRC from Mr. C. M. Stallings,, Vice President - Power Supply and Production Operations, VEPCO, dated September 12, 1977.

10.0-2 NPSH Report - Surry 1 & 2, attached to letter to Mr. Edson G. Case, Acting Director of Nuclear Reactor Regulation, U.S. NRC from Mr. C. M. Stallings, Vice President - Power Supply and Production Operations, VEPCO, dated Nov9-m_ber 22, 1977.

( !

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0 (I) er, (I) w 0::: -

a...

_J 0

a:

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w J::

z -

a:

0 z

0 u rt TIME AFTER LOCA CSECONOSJ FIO. 10.0-1 PRESSURE TRANSIENTS CONTAINNENT INrEORITY LOCA

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I Question 11.0 Compare the flow rate in gpn versus time of the LHSI pumps throughout the LOCA for the.present LHSI system and the proposed LHSI system modi-fication. Provide the change in peak clad temperature that may occur vith the proposed system modifications. Provide either a new ECCS analysis for the redesigned ECCS system or a sensitivity analysis to show that the previous ECCS analysis conservatively bounds the performance of the modified system *.

Response --<

The comparison is presented in Figure 11.0-1. For the present LHSI system, the LHSI flow is throttled by the operator to 3500 gpm maximum for the recirculation mode.

The peak clad temperature effect vill be discussed separately in a later response.

T


+--- ----*--*--


 :-_ : FIGURE-j1*.o.::,:,-:_:.. *:_

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2000

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