ML20247M636
| ML20247M636 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 11/30/1988 |
| From: | Gido R LOS ALAMOS NATIONAL LABORATORY |
| To: | NRC |
| Shared Package | |
| ML20246A841 | List: |
| References | |
| CON-FIN-A-7272 NUDOCS 8906050095 | |
| Download: ML20247M636 (21) | |
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., MADDAM NECK COMBUSTION GAS CONTROL COGAP ANALYSIS 4 (NRC FIN A7272 Letter Report)
K, by R. G. Gido Safety Assessment Group Nuclear Technology and Engineering Division Los Alamos National Laboratory t- University of California Los Alamos, New Mexico 87545 November 1988 e
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CONTENTS Page ABSTRACT . . . .... . ... . .. . ...... 1
- 1. INTRODUCTION .... ..... . .. ... . . 1 II. COGAP INPUT - . .... .. .. . . . . 2 A. Containment Representation . . . .. . . .. . 2 B. Air injection .. . .. . .... 2 C. Radiolysis of Water ......... ... .. .. 3 D. Metal-Water Reaction . . ..... . .. ... 4 E. Corrosion of Metals ...... .... . . . 5 Ill. CALCULATED RESULTS .......... ..... .. .... 6 IV. CONCLUSIONS AND RECOMMENDATIONS . . . . . ....... . 8 ACKNOWLEDGMENT ... ... . . . . ... 9 REFERENCES .. ....... . . ...... . . 9 APPENDIX A. COGAP OUTPUT . . . . . . . .. .. .. ..... 10 1
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L HADDAM NECK COMBUSTION GAS CONTROL COGAP ANALYSIS (NRC FIN ~A7272 Letter Report) by i R. G. Gido ABSTRACT Hydrogen concentrations following a design-basis loss-of-coolant accident LOCA' for the Haddam Neck- Plant : are
' es t 'ima t ed. The' analyses were performed with the US Nuclear Regulatory . Commission (NRC) COGAP code with conservat ive code-input paiameter values based on NRC Standard Review Plan guidelines.
The calculated results indicate that the hydrogen concentration (a) reaches 4 v/o af ter 180 days (6 months),
(b) can be reduced to approximately. 2.5 v/o with air injection'.so that the: containment pressure is increased by 10 psi, which is a limiting consideration,'and (c) reaches 4 v/o af ter the air injection at 840 days (28' months) af ter the beginning of the accident.
We confirmed our calculated results by comparing them with results submitted by the plant utility. However, our calculated results are based on more conservative assumptions. i
- 1. INTRODUCTION The purpose of this analysis was to estimate the hydrogen concentrations following a design-basis loss-of-coolant accident (LOCA) for the Haddam Neck Plant using (a) the US Nuclear Regulatory Commission (NRC) COGAPI code, and I (b) acceptably conservative code-input parameter values based on Sec. 6.2.5,
" Combustible Gas Control in Containments," of NRC Standard Review Plan Guidelines 2 and USNRC Regulatory Guide 1.7.8 The request for this plant-specific analysis of Haddam Neck came from J. S. Guo of the NRC, who gave us (a) basic guidelines for COGAP input parameters
- and @l_the utility combustible gas control evaluation.*
- Input information and personal Communication, J. S. Guo, US Nuclear Regulatory Commission (October 1988).
_ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ - . - _ J
In addition, NRC Branch Technical Position ASB 9-28 was used to define the value of 16 000 h used for reactor operating history.
II. 00 GAP INPUT This section discusses the COGAP input parameters that are (a) of primary importance, (b) dif ferent f rom parameter values used in Ref. 4, or (c) require detailed explanat ion. Other parameter values can be obtained f rom the code output in Appendix A.
A. Containment Representation The containment is represented by a single volume of air with the initial conditions f rom Ref. 4 of (a) 2.125.x 105 ft3, which is the total containment f ree voltme of 2.232 x 105 ft* less the lower-annulus compartment volume of 0.107 x 105, (b) 120'F, (c) 16.5 psia, and (d) zero relative humidity. In addition, the ef fect of steam is ignored for the complete calculation as is (conservatively) assumed in Ref. 4.
A second volume at standard ambient pressure and temperature was modelled to represent the outside atmosphere so that the effect of air injection could be estimated. See Sec. II.B. Air is injected f rom the atmosphere to the containment through a COGAP connection with input specification for the (a) flow rate from the outside atmosphere and (b) the beginning and ending of the flow.
B. Air injection When the hydrogen concentration reaches 4 v/o for the first time, Ref. 4 uses air injection to reduce the concentration and postpone the time when the limiting value of 4 v/o is reached again. The details of the air injection were not given in Ref. 4 except that the quantity of air injected was limited so that the containment pressure would not increase by more than approximately 10 psi.
To determine the mole addition (AN) that corresponds to an increase in pressure (AP), the equation P V = N R T was used to provide AN = APV RT
^
where P is pressure, V is volume, N is the number of Ibm-moles, R is the gas constant, and T is temperature. This equation gives AN = 3535.8 lbm-mole for
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values of AP. = 10 psi, V '= 2.125 x 105 ft8, T = 560*R (100*F), and R =-1545.4 (f t-lb )/(*R f Ibm-mole). This. corresponds to 1.368'x 105 scf (T = 70*F, P = 14.7 psia). To. convert this to a volumetric flow rate, it was arbitrarily assumed that the air injection occurred over three days, which resulted in an injection rate of 317 scfm. In addition, the air-injection was arbitrarily assumed to begin' when the containment hydrogen concentration reached a value slightly less than 4 v/o the first time To summarize the specifics, air injection was ' simulated in this analysis with the-following COGAP input: (a) a large volume to represent the surrounding atmosphere, (b) .a conr.ect ion from the atmosphere (Volume No. 2) to the
- containment (Volume No.1); .(c) initiation of flow f rom Volume No. 2 to Volume No.1, that is, the air injection, at 180 days-specified by the variable CON (4).
the recirculation-fan-start time: (d) termination of the flow at 183 days specified by the variable CON (6), a feature added to COGAP for this analysis; and (e) a volumetric flow rate of 317 scfm from the atmosphere to the containment.
C. Radiolysis of Water The following is the COGAP input used to calculate the hydrogen generated by radiolysis of water. In addition, the sources of the parameter values and a comparison with corresponding values used in Ref. 4 are given.
- 1. -Reactor Thermal Power. 1825 MWt was used based on communicat ion f rom Guo and Ref. 4.
A sensitivity study of the effect of this parameter showed that the hydrogen concentration for this problem, with all hydrogen sources modelled, is almost directly proportional to the power. Specifically, an increase in the power of 2% (that is, from 1825 to 1861.5 MWt )
resulted in.an increase in the hydrogen concentration at 180 days of 1.5% (that is, from 3.95 to 4.01 v/o). This occurs because the hydrogen generated by radiolysis is (a) directly proportional to the power (see Ref. 1) and (b) is the major component of the total hydrogen (see Sec. til).
- 2. Reactor Operating Time. 16 000 h was used based on NRC Branch Technical Posi t iorLASB 9-2.5 It is not clear how this parameter was taken into account in the Ref. 4 analysis.
A sensitivity study of the effect of this parameter showed that the ;
hydrogen concentration for this problem, with all hydrogen sources modelled, is not very sensitive to the operating iife. Specifically.
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- a. Increasing the operating life by 20% (that is, f rom 16 000 h to I 19 200 h) resulted in an increase in the hydrogen concentration at 180 days of 1.5% (that is, from 3.95 to 4.01 v/o),
- b. Decreasing the operating life by 20% (that is, from 16 000 h to I
(
12 800 h) resulted in a decrease in the hydrogen concentration at 180 days of 2.0% (that is, from 3.95 to 3.87 v/o).
- 3. Radiolytic Hydrogen Yield G(H2). 0.5 molecules /(100 eV) was used based on Regulatory Guide 1.7. Reference 4 used a value of 0.44. The l difference between our value and the Ref. 4 value for this parameter would cause our radiolytic hydrogen to be greater by approximately the ratio 0.5/0.44 = 1.14, which is equivalent to a difference of 14%. In Sec. Ill, it is shown that our value is higher by 11% at 180 days.
- 4. Fission Product Radiation Energy Absorbed by Coolant. A value of 10% l of the fission-product decay energy was used. This value is the acceptable value specified in NRC Regulatory Guide 1.72 and was used in Ref. 4 D. Metal-Water Reaction The fuel-element cladding for Haddam Neck is Type 304 stainless steel and Ref. 4 calculates that a metal-water reaction of 5% of the cladding produces 56.5 lbm of hydrogen. Guo recommended a value of 56 lbm. To generate this amount of hydrogen with COGAP, an equivalent combination or zirconium mass and the per cent of this mass reacted is needed.
The zirconium-water reaction used in COGAP is Zr + 2H,0 = Zr0, + 2H2 + Energy ,
which results in two moles of hydrogen being generated for each mole of zirconium reacted. Using molecular weights [lbm/(ibm-mole)) of 91.22 for zirconium and 2.02 for hydrogen results in 1 lbm of zirconium generating 0.0443 lbm of hydrogen, that is, 2 x 2.02/91.22. Using this value and 5% for ,
the per cent zirconium reacted, the equivalent zirconium mass to be used in the COGAP input to generate 56 lbm of hydrogen is given by
1 56 (Ib,- H,)
Zr " 0.0443 (Ibm-H,)/(Ibm-Zr) x 0.05
= 25282 lbm-Zr .
The adequacy of this approach was confirmed by the result of our COGAP calculation because 56.2 lbm of hydrogen from the metal-water reaction was calculated. See Sec. Ill.
E. Corrosion of Metais The corrosion of metal surfaces was modelled based on information from Guo. This information actually came f rom Ref. 6 and corresponds to that provided in the original plant license application submitted approximately 15 yr ago, included are the following for aluminum and zinc component sur f aces (a) metal surface area in ft2, (b) metal mass in Ibm, and (c) corrosion rate in Ibm / day. For use in COGAP, this information was converted into the appropriate format that is, sur f ace area in f ta, surf ace thickness in inches, and corrosion rate in mi1/yr. Table i summarizes the metal-sur f ace corrosion information for this analysis including the basic information f rom Guo and a COGAP input.
Using the values in Table I resulted in amounts of hydrogen generated by metal corrosion significantly larger than from the analysis of Ref. 4; see Sec. Ill. This resulted probably f rom Ref. 4 (a) assuming that the original aluminum and zinc surfaces have oxidized over the 15-yr operating life of the plant, and the only surf aces that might be oxidized woWd be the zinc-based j primers used to coat steel surf aces, (b) corrosion occurring only when the containment temperature exceeded 1.20*F, and (c) the containment temperature i exceeding 120*F for only a short time.
It is interesting to note that the zine surface area used in Ref. 4 is considerably larger (58 775 f t2) than that provided by Guo (27192 f t2). To investigate the effect of an increased zinc surface area, the increased <
l (Ref. 4) zinc surface area was used with everything else kept the same, j including, the aluminum representat ion. the zinc thickness, and the zine I corrosion rate. This resulted in a hydrogen concentration of 4 v/o hydrogen being reached in about 130 days vs 180 days with the smaller (Guo) zine sur f ace )
area. 1
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U TABLE i HADDAM NE'CK METAL-CORROSION INFORMATION L Component Surface Parameter Aluminum Zinc
- Surf ace Areaa ,b:(f t8)' 39705. 27192.
O Massa (Ibm)- 18977. 1700.
- Density (Ibm /ft3) 168.5 445.5 Thicknessb,c ('in.) 0.0340 0.00168 i
Corrosion'Ratea (lbm/ day) 0.195 66.9 Corrosion Rateb.d (mil / year) 0.1277 24.19 a From Guo.
b COGAP input.
c Based.on the mass, surface area, and density.
d Based on the corrosion rate, density, and area. I lit. CALCULATED RESULTS The primary COGAP calculated output with the input described in Sec. 11 is presented in Appendix A. Handwritten comments have been added to the output to -
. emphasize' input and output detaiIs. =
.The calculated results indicate that the hydrogen concentration reaches 4 v/o af ter 180 days (6 months), (b) can be reduced to ~2.5 v/o after air '
injection Euch that the containment pressure increases -10 psi, which is a limiting coh ideration, and (c) reaches 4 v/o after the air injection at 840 days (28 months) after the beginning of the accident.
Table 11 is a comparison of our calculated values for hydrogen generated after 180' days with those presented in Ref. 4. The primary differences between l
'the calculated results and the reasons for the differences are as follows.
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TABLE II
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COMPARIS0N OF NYDR0 GEN GENERATED AFTER 180 DAYS .
(Los Alamos vs Ref. 4) ;
Ref. 4 Los Alamosa lbm
_Sou r ce ~ lbm_ Ibm _ lbm-mole Diff.b Radiolysisc 326. 363.2 179.8 37.2 L
L Metal Water Reactiond- 56.5 56.2~ 27.81 -0.3 l
Corrosion of Metal Surfacese 4.7 56.5 28.0 51.8
. Hydrogen.in Primary Coolant and in Pressurizer Vapor Spaced 1.5 1. 5 0.75 0.0
-Total after 180 Days 389.0 477.0 236.3 88.7 a Los Alamos National Laboratory COGAP calculation.
b Los Alamc3 value minus the Ref. 4 value.
c Note that the ratio of the Los Alamos to the Ref. 4 radiolysis value is 363/326 = 1.11, which is approximated by the ratio of the radiolytic hydrogen yields used, that is, 0.5/0.44 = 1.14 d This' hydrogen is released to the containment in the first_ day.
e This source of hydrogen treated very differently by Los Alamos and Ref 4; see Sec. 11.
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- 1. Our hydrogen generated by radiolysis is greater because our radiolytic hydrogen yield constant is higher. See Sec. fl.C. Note that our value l j
of 0.5' molecules /(100 eV) is the acceptable value from NRC Regulatory Guide 1.7.
2.. Our oxidation of containment surfaces is greater primarily because our corrosion was independent of containment temoe ature, whereas Ref. 4 assumed there was corrosion only when the temperature is above 120*F, which occurs for a short time.
To verify the adequacy of our COGAP input as described in Sec. II, the following supportive calculations were performed.
- 1. Time-step size was varied to see if the results changed significantly.
Specifically, the effeet of the time-step size variation on the hydrogen concentration at 180 days is
- a. 3.95 v/o with the time-step sizes of the basic calculation (the output is presented in Appendix A), 'l
- b. 3.97 v/o wi th the time-step sizes of the basic calculation multiplied by 0.5, and
- c. 3.99 v/o with the time-step sizes of the basic calculation multipiied by 0.1. ]
This sensitivity study established the adequacy of the basic time-step used for our calculation.
- 2. To verify the accuracy of the modelling, calculations were performed with each of the hydrogen sources active by itself with the other-sources deactivated. Specifically, the hydrogen generated by radiolysis, fuel cladding-water reaction, and containment-sur f ace corrosion were verified.
IV. CONCLUSIONS AND RECOMMENDATIONS i
For a design-basis LOCA for the Haddam Neck Plant, calculations with the ,
COGAP code using conservative code-input parameter values resulted in the '1 following values of the hydrogen concentration.
- 1. 4 v/o after 180 days (6 months),
- 2. Approximately 2.5 v/o after air injection f rom 180 to 183 days such that the containment pressure increases approximately 10 psi (actually 9.4), which is a limiting consideration, and
- 3. 4 v/o af ter the air injection at 840 days (28 months) after the beginning of the accident. '
Our calculated results are consistent with the-results submitted by the plant utility. However, our calculated results use more conservative assumptions and, as result, reach 4 v/o at'earIier times.
ACKNOWLEDGMENT J. S. Guo of the US Nuclear Regulatory Comission, Of fice of Nuclear 'i Reactor Regulation provided valuable guidance in the formulation of this problem.
REFERENCES
- 1. R. G. Gido "COGAP: A Nuclear Power Plant Containment Hydrogen Control System Evaluation Code," Los Alamos National Laboratory report LA-9459-MS,
.NUREG/CR-2847 (January 1983).
~2. " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," LWR Edi t ion, Sect ion 6.2.5, " Combust ible Gas Cont rol in Containments," Of fice of Nuclear Reactor Regulatory Comission report NUREG-75/0876, Rev. 1 (May 1980).
- 3. " Control of Combustible Gas Concentrations in Containments Following a Loss-of-Coolant Accident," US Nuclear Regulatory Comission Regulatory Guide 1.7 (November 1978).
- 4. " Attachment No. 2, Haddam Neck Plant Combustible Gas Control Evaluation,"
Docket No. 50-213 (March 1983).
- 5. " Residual Decay Energy for Light Water Reactors for Long-Term Cooling " US Nuclear Regulatory Comission Branch Technical Position ASB 9-2.
- 6. Letter f rom J. F. Opeka to C.1. Grimes, " integrated Safety Assessment Program" (November 17, 1986).
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APPENDIX A' COGAP OUTPUT.-
The attached output Llisting-resulted f rom the code input (a) discussed in L. .
Sec. II; (b) echoed at the beginning of the output, and (c) interpreted .~in the _ I
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