ML20203E075
| ML20203E075 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 02/06/1998 |
| From: | Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Quay T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19317C896 | List: |
| References | |
| AW-98-1202, NUDOCS 9802260249 | |
| Download: ML20203E075 (88) | |
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l Westinghouse Energy Systems yjt)g y,,,, g og33 Electric Corporation AW 981202 I
February 6,1998 i
Document Control Desk
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'U.S. Nuclear Regulatory Commission i
Washington, DC 20555
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A ITENTION:
MR. T. R. QUAY APPL.lCATION FOR WITilllOLDING PROPRIETARY INI ORMATION I ROM PUllLIC DISCLOSURE SUlijECT:
SSAR 6.2 MARKUP AND EVALUATION MODEL CilANGES
Dear Mr. Quay:
The application for withholding is submitted by Westinghouse Electric Company, a division of CilS Corporation (" Westinghouse"), pursuant to the provisions of paragraph (b)(1) of Section 2.790 of the Commission's regulations, it contains commercial strategic informatioa proprietary to Westinghouse and customarily held in confidence.
The proprietary material for which withholding is being requested is identified in the proprietary version of the subject report, in conformance with 10CFR Section 2.790, Afridavit AW 981202 accompanies this application for withholding setting forth the basis on which the identified proprietary information may be withheld from public disclosure.
Accordingly, i; is respectfully requested that the subject information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the Commission's regulations.
Correspondence with respect to this application for withholding or the accompanying affidavit should reference AW 981202 and should be addressed to the undersigned.
Very truly yours, lirian A. McIntyre, Manager Advanced Plant Safety and Licer,ing jml-cc:
Kevin Ilohrer -
NRC OWlH - MS 12E20
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A PDR
COPYl(IGilT NL l'ICI:
't he reports transmitted herewith each bear a Westinghouse copyright notice. The NI(C is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generie and plant specific seriews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFit 2.790 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non proprietary versions of these reports, the NI(C is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, D.C. and in local public document rooms as may be required by NI(C regulations if the number of copies submitted is insullicient for this purpose. Copies made by the NI(C must include the copyright notice in r.!! instances and the proprietary notice if the original was identified as proprietary, ww
1 l'HOPRil:TARY INI'ORMATION NOllCI:
Transmitted herewith are proprietary and/or non proprietary versions of documents furnished to the NitC in connection with requests for generic and'or plant specin: review and approval.
In order to conform to the requirements of 10 Cl R 2.790 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the croprietary information has been deleted in the non proprietary versions, only the brackets rernain (the information that was contained within the brackets in the proprietary versions having been deleted). The justl0 cation for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f) contained within parentheses located as a superscript immediately following the bra 'iets enclosing each item of information being identined as proprietary or in the margin opposite such information. These lower <,ase letters refer to the types of information Westinghouse customarily holds in con 0dence identined in Section (4)(ii)(a) thorough (4)(li)(f) of the affidavit accompanying this transmittal pursuant to 10 CFR2.790(b)(1).
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AW.981202 AFllDAVIT i
COMMONWi!Alifil OF Pl!NNSYINANIA:
ss COUNTY OF Al.Ll! Gill!NY:
liefore me, the undersigned authority, personally appeared tirlan A. McIntyre, who, being by me duly sworn according to law, deposes and says that he is authorlied to execute this Affidavit on behalf of Westinghouse filectric Company, a division of CI!S Corporation (" Westinghouse"), and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:
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lirlan A. McIntyre, Manager Advanced Plant Safety and Licensing Sworn to and subscribed before me this _ /3 fl_ day o( kJ A d l/s
,1998 Notary _Publit._ _'
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AW.981202 (1)
I am Manager. Advanced Plant Safety And I.icensing, in the New Plant Projects Division, of the Westinghouse Electric Company, a division of CilS Corporation (" Westinghouse"), and as such, I have been specifically delegated the function of reviewing tbc proprietary infonnation sought to be withheld from public disclosure in connection with nuclear power plant licensing and rulemaking proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Energy Systems ilusiness Unit.
(2)
I am making this Affidavit in conformance with the provisions of 10CFR Section 2.790 of the Commission's regulations and in conjunction with the Westinghouse application fbr withholding accompanying this Affidavit.
0)
I mye personal knowledge of the criteria and procedures utilired by the Westinghouse Energy Systems ilusiness Unit in designating information as a trade secret, privileged or as confidential commercial or financial infbrmation.
(4)
Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the ibliowing is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
(i)
The infonnation sought to be withheld from public disclosure is owned and has been held in.mlidence by Westinghouse.
(ii)
The information is of a type customari!y held in onfidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types er nnation customarily held in confidence by it and, in that connectior.,
utiliics a system to determine when and whether to hold certain types of information in confidence, The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:
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AW 981202 (a)
The information rewals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors whhout license from Westinghouse constitutes a competitive economic advantage over other companics.
(b)
It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimitation or improved marketability.
(c)
Its use by a competitor would redure his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d)
It reveals cost or price information, production capacit;cs, budget levels, or commercial strateg!cs of Westinghause, its customers or suppliers.
(c)
It reveals aspects of past, prese;t, or future Westinghouse or customs funded development plans and programs of potential commercial value to Westinghouse, (f)
It contains patentable ideas, for which patent protection may be desirable, There are sound policy reasons behind the Westinghouse system which include the following:
(a)
'the use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors, it is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
(b)
It is information which is marketable in many ways. 'The extent to which such information is available to competitors diminishes t: e Westinghouse ability to sell products and services involving the use of the information, wn.,r
AW.981202 (c)
Use by our coiapetitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
(d) 1:ach component of proprietary information peninent to a particular competitive advantage is potentially as valuable as the total competitive advantage, if competitors acquire components of proprietary information, any one component may be the key to the entire purrle, thereby depriving
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Westinghouse of a competitive advantage.
(c)
Unrestricted disclosure would jeopardire the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.
(f)
The Westinghouse capacity to invest corporate assets in research and development depends upon the success in o'etaining and maintaining a competitive advantage.
(hi)
'the information is being trans.nitted to the Commission in con 0dence and, under the provisions of 10CFR Section 2.790, it is to be received in con 0dence by the Commission.
(iv)
The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.
(v) linclosed is Letter DCP/NRCl247 (NSD NRC 98 5560), February 6,1998, being transmitted by Westinghouse lilectric Company (W), a division of Clis Corporation
(" Westinghouse"), letter and Application for Withholding Proprietary Information from Public Disclosure, lirlan A. McIntyre @), to Mr. T. R. Quay, OfHce of NRR. The proprittary information as submitted for use by Westingnouse !!!ectric Company is in response to questions concerning the AP600 plant and the associated design certincation application and is exrteted to be applicable in other licensee submittals in response to certain NRC requirements for justi0 cation of licensing g
advanced nuclear power plant designs.
wn.,,
AW.981202 This information is part of that which will enable Westinghouse to:
(a)
Demonstrate the design and safety of the AP600 Passive Safety Systems.
(b) listablish applicable verification testing methods.
Design Advanced Nuclear Power Plants that meet NRC requirements.
(d)
IIstablish technical and licensing approaches for the AP600 that will ultimately result in a certilkd design.
(c)
Assist customers in obtaining NRC epproval for future plants.
I urther this information has substantial commercial value as follows:
(a)
Westinghouse plans to sell the use of similar information to its custc ners for purposes of meeting NRC requirements for advanced plant licenses.
(b)
Westinghouse can sell su port and defense of the technology to its customers r
in the licensing process.
Public disclosure of this proprieta < information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar advanced nuclear power designs and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would enable others to use the intbrmation to meet NRC requirements for licensing documentation without purchasing the right to use the information, me.,.c
AW.981202 J
I i
1he development of the technology described in part by the infortnation is the result of applying the results of many years of experier.:e in an intensive Westinghouse effort
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and the expenditure of a considerable sum of n:oney, in order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a sign 10eant manpower effort, 4
having the requisite talent and experience, would have to be expended for developing I
analytical methods and receiving NRC ap;<roval for those methods, i
17urther the deponent sayeth not.
4 E
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ATTACHMENT 1 SSAR 6.2 MARKUPS i
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- 6. Engineered Sdely rectures De reactor coolant loop is surrounded by structural walls of the containment intemal j
stmetures. Dese stmetural walls are a minimum of 2 feet 6 inches thick and enclose ti,e reactor veuel, steam generators, reactor coolant pumps, anJ the pressuriter, De containment sessel is designed and constructed in accordance with the ASMii Code, Section Ill, Subsection Nii, Metal Containment, including Addenda through 1989, as desenbed in subsectmn 312.
Structural steel non pressure retaining paru such as ladders, walkways, and handrails are designed to the requirements for steel structures defined in subsection 3.8.4.
The design features provide adequate containment sump levels following a design basis event as desenbed in subsection 3.4.
Containment and subcompartment atmospheres are maintained during normal opetation within prescribed pressure, temperature, and humidity limits by means of the containment air recirculation systern (VCS), and the central chilled water system (VWS). The recirculation system cooling coils are provided with chilled water for temperature control. The filtration supply and exhaust subsystem can be utilized periodically to purge the containment air for prenure control. Periodic inspection and maintenance verify functional capability.
6.2.1,1,3 Design F. valuation 20 and 32, The Westinghouse-GOTillC MGOTillC) computer code (Reference 1)$ is a co,nputer W
prograrn for modeling multiphase Dow in a containment transient analysis. It solses the conservation equations in integd form for mass, energy, and momentum for multicomponent now. He momentum conservation equations are written separately for each phase in the now fielo (drops, liquid pools, and atmosphere vapor). De following terms are included in the momentum equation: stoiage, convection, surface stress, body force, boundary source, phase interface source, and equipment source.
To model the passhe coohng features of the Ap600, several assumptions are made in creating the plant decks. De external cooling water does not completely wet the containment shell, thert. ore, both wet and dry sections of the shell are modeled in the WGOTli!C analyses. The analyses use conservative coverage fractions to determine c~aporative cooling.
lleat conduction from the dry to wet section is considered in the analysis. The combmation of passive containment cooling system coverage area and heat conduction from the dry to wet sections is explained in Chapter 7 of Reference 20. The analyses conservatively assume that the extemal cooling water is not initiated until 337 seconos into Jie transient, allowing time to initiate the signal and to fill the headers and weirs and to develop the now down the containment side walls. The effects of water Dowing down the shell from gravitational forces are explicitly considered in the analysis.
Revision: 14 June 27,1997 6.2 2
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- 6. Enginnred Saf;ty lit:res The containment imtial conditions of prenure, temperature, and humidity are provided in Table 6.2.1.1 2.
For the LOCA events, two double ended guillotine reactor coolant system pipe breaks are analyred. De breaks are postulated to occur in either a hot or a cold leg of the reactor coolant system The hot lef break remits in the highest blowdown peak preuure. The coid leg break results in the higher post blowdown peak pressure. De cold leg break analysis includes the long term contnbution to containment preuure from the sources of stored energy, such as the steam generators.
The LOCA man and energy releases described in subwction 6.2.13 are used for these calculations.
For the MSLB event, a representative pipe break spectrum is analyzed. Various break sites and power levels are analyzed with the WGOTillC code. The MSLil mass and energy releases desenbed in subsection 6.2.1.4 are used for these calculations.
The results of the LOCA and MSLI) postulated accidents are provided in Table 6.2.1.13. A mmparison of the containment integrity analyses results to General Design Criterion 38 and the Acceptance Critena presented in Reference 25 are also provided in Table 6.2.1.13. He g'
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pre m.Tt-m t ' a s The containment pressure response for the peak pressure steam line break case is provided in Figure 6.2.1.1 1. De temperature response for this case is provided in Figure 6.2.1.12.
Figures 6.2.1.13 and 6 2.1.14 provide the containment preuure and temperature response for the peak temperature steam kne break case.
R e G er %e. 2.0 SM.cn 4
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' %c panive internal containment heat sini data used in the WGOTil!C analyses is presented 4
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' + uih621 b7 Tne containmen' preuure and temperature responses to a double ended cold leg guillotine are presented in Figures 6.2.1.1 $ and 6.2.1.1-6 for the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> portion of the transient and Figures 6.2.1.17 and 6.2.1.18 for the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> transient.
The containment preuure and temperature response to a double ended hot leg guillotine break are presented in Figures 6.2.1.19 and 6.2.1.1 10. Data for both metallic and concrete heat sinks are presented. He physical propenies of the materials corresponding to the heat sink information is presented in Table 6 2.1.18.
The instrumentation provided inside containment to monitor md record the containment pressure and temperature is found in Section 7.5.
6.2.1.l.4 External Preuure Analpis Cenain design basis events and credible inadvenent sptems actuation have the potential to result in containment externd pressure lords. Evaluations of these esents show that a loss of all ac power sources during estreme cold ambient conditions has the potential for creating the worst case external pressure load on the containment sessel. This event leads to a reduction in the internal containment heat loads from the reactor coolant system and other active components. thus resulting in a temperature reduction wwhin the containment and an Resision: 14 W Westinghouse 6.2 3 June 27,1997
6.1:ngineered Safety Fe:t:res foi a gisen time penod is determined from the difference between the energy required to raise the temperature of the incoming flow to saturation and the sum of the decay heat, core stored energy, reactor coolant system metal energy and SG mass and metal energy release rates. The energy release rate for the available break now is determined from a companson of the total energy available release rate and the energy releaw rate auuming that the break flow is IOO percent saturated steam. Sateated steam releases masimite the calculated containment preuuritation.
6.2.1.3.2.4 Single Failure Analysis Mato M I No single failure is auumed in the mau and enngy release calculations. The safety injection acyd system for the Ap600 is panive, as opposed it active pumped safety injection systems for a conventional pWR. As a result, there is r.o single failure postulated for the mau and energy I"*IN release analysis. The effects cf a single failure are taken into account in che containment analysis of subsection 6,2.1.1.
6.2.1.3.2.5 Stetal. Water Reaction Consistent with 10 CFR 50, Appendix K criteria. the energy release associated with the zirconium water exothermic reaction has been considered.
The LOCA peak claddmg temperature analysis, presented in Chapter 15, that demonstrates compliance with the Appendix K cnteria demonstrates that no appreciable level of zirconium oxidation occurs.
This lesel of reaction has been bounded in the containment mass and ene o release analysis by incorporating the heat of reaction from 1 percent of the rirconium surrounding the fuel.
This exceeds the level predicted by the LOCA analysis and results in additional conservatism in the man and energy ielease calculations.
6.2.1.3.2.6 Energy Iv/entories Inventones of the amount of mass and energy released to containment dunng a postulated LOCA are provided in summary Tables 6.2.1.3 2 through 6.2.1.3 7.
6.2.1.3.2.7 Additional information Required for Confirmatory Analysis System parameters and hydraulic characteristics needed to perform confirmatory analysis are provided in Table 6.2.1.3 8 and Figures 6.2.1.31 through 6.2.1.3-4.
6.2.1.4 Slass and Energy Release Analysis for Postulated Secondary. System Pipe Rupture inside Containment Steam line ruptures occumng inside a reactor containment stmeture may result in significant releases of high energy fluid to the containment end:onment, possibly resulting in high containment temperatures and pressures. The quantitative nature of the releases following a steam line rupture is dependent upon the configuration of the plant steam system, the containment design as well as the plant operat'ng conditions and the size of the rupture. This section desenbes the methods uwd in determining the contaisment responses to a variety of Resision: 14
[ W85tlfigh00$8 6.21I June 27,1997
Revloed paragraph for SSAR 6.2.1.3.2.4 The assumptions for the containment mass and energy release analysis are intended to i
maximize the calculated release. A single failure could reduce the flow rate of water to the RCS, but would not disable k passive core cooling MIFor example, if one of the two parallel valves from the CMT were to fall to open, the injection flow rate would be reduced and, as a result, the break mass release rate would decrease. Therefore, to maximize the releases, the AP600 mass and energy rt.sase calculations do not y
assume a single failure. The effects of a single failure are taken into account in the containment analysis of subsection 6.2.1.1.
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t,. I:ngineered safety I'est:res some of the Guid in this solurne will Rash into the steam pnerator, providing additional secondary Guid that may exit out the rupture.
De feedwater addition that occurs prior to closing of the feedwater line isolation vahes innuences the steam pencrator blowdown in several ways. First, the rapid addition increases the amount of entrained water in large break cases by lowering the bulk quality of the steam generator inventory. Second, because the water entering the steam generator is subcooled, it lowers the steam preuure, thereby reducing the flow rate out the break. Finally, the increased now rate causes an increase in the heat transfer rate from the primary to secondary system, sesulting in greater energy being released out the break. Since these are competing effects on the total mau and energy release, no worst case feedwater transient can be denned for all plant conditions. In the results presented, the worst effects of each vanable have been used.
For esample, inoisture entrainment for each break is calculated auuming conservatisely small r dwater additions so that the entrained water is minimized or zero. Detennination of total ee
, team generator inventory is based on conservatively large feedwater additions, as explained in subsection 62.14.32.
The unisolated feedwater line volumes between the steam generator and the isolation valves serve as a source for additional high energy Guid to be discharged through the pipe break.
This volume is accoun'.ed for in the mau and energy release data presented in subsection 6.2.1.412.
6.2.1.4.1.3 Startup Feedwater System Design Within the nrst minute following a steam line break, the startup feedwater system may be initiated on any one of several protection system signals. De addition of startup feedwater to the steam generators increases the secondary man available for release to the containment, as well as the heat transferri to the secondary Guid. De effects on the steam generator mass are maximized in the calcula; ion desenbed in subsection 6.2.1.4.3.2 by assuming full stanup feedwater now to the faulted steam generator starting at time zero from the safeguard 9 stem (s) signJ or low geam generator level reactor trip and continuing until automatically terminated.
Postulated Hreak T pe, Sire and Location 6.2.1.4.1.4 3
Postulated Hreak Type Twe types of postulated pipe niptures are considered in evaluating steam line breaks.
First is a split rupture in which a hole opens at some point on the side of the steam pipe ee-g
- %d-but does not result in a complete severance of the pipe. A single, distinct break area is fed ut..fonnly by both steam generators until steam line isolation occurs, The blowdown now rates from the individual steam generators are interdependent, since Guid coupling esists between the steam lines. Because now limiting orifices are provided in each steam generator, the largest split ru; e can hase an effective area prior to isolation, that is no greater than the throat area of th N "i restrictor times tite number of steam generators.
Revision: 14 3 Westiflgh0U$6 6.2 13 June 27,1997 i
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- 6. Engineered S:f:ty Fe:t:res Following isolation, the effective break area for the steem generator with the broken line can be no greater than the flow restrictor throat area.
The second break type is the double ended guillotine mpture in which the steam pipe is compt tely severed and the ends of the break displace from each other. Guillotine ruptures are characterized by two distinct break locations, each of equal area, but being fed by different steam generators. The largest guillotine rupture can have an effective area per steam generator no Freater than the throat area of one steam line now restrictor.
Postulated fireak Size It controls the rate of releases Break area is also important when evaluating steam line 3.
to the containment, and induences the steam pressuie t
< and the amount of entrained water in the blowdown Dow. De data presented in this sectio include releases fcr four breaks at each of four initial power levels. Included are three dc le ended ruptures and one split rupture, as follows:
ocmMAk A full double ended pipe rupture downstre, of the steam line now restrictor. For this case, the atual break area equals the er ss sectional area of the steam line, but the blowdown from the steam generator wit the broken line is controlled by the flow restnctor throat area (1.388 square fee The reverse now from the intact steam g
generator is controlled by the smaller of the pipe cross section, the steam stop valve <, eat area, or the total now restrictor throat area in the intact steam generator. He reverse now has been conservatively assumed to be controlled by the now restrictor in the intact loop steam generator.
An intennediate size double-ended mpture having an area of 0.4 square feet.
A small double ended rupture having an area of 0.1 square feet.
nok A split rupture representing the largest break which canggenerate a steam line 4
isolation signal from the primary protection equipment. Steam and feedweter line isolation signals are generated by high containment pressure signals for this type of break.
Table 6.2.1.41 lists the spectrum of secondary system pipe ruptures analyzed.
Postulated Break 1,ocation Break location affects steam line blowdown due to the pressure losses which occur in the length os piping between the steam generator and the break. De effect of the pressure loss is to reduce the effectisc break area seen by the steam generator. Although this reduces the rate of blowdown, it would not signincantly change the total release of energy to the containment. Therefore, piping loss effects are conservatively ignored in the blo.. awn resultt Revision: 14 June 27,1997 6.2-14 3 Westlrigh00Se
- 6. Ergineered S:f;ty I'e:t:res Coolant S 5 tem Sletal lleat 6.2.1.4.1.7 Steam Generator Reserse IIcat Transfer and kcacto 3
Capacity Once steam line isolation is complete. the steam generator in the intact steam loop becornes a source of energy that can be transferred to the steam generator with the broken line. This energy transfer occurs through the pnmary coolant.
As the primary plant cools, the temperature of the coolant Howing in the steam generator tubes drops below the temperatur of the secondary Guid in the intact umt, resulting in energy being returned to the pnmari coolant. This energy is then available to be transferred to the steam generator wiv the brot.n steam line.
Similarly, the heat stored in the metal of the reactor coolant piping. the reactor assel. ".id the reactor coolant pumps is transferred to the primary coolant as the plant cooldown pogresses.
His energy also is available to be transferred to the steam generator with the broken line.
The effects of both the reactor coolant system metal and the reverse steam generator heat transfer are included in the results presented Rep \\nce, wh dacke.A para $raph 6.2.1.12 Description of lilowdown Model ct n ck q d ed e. ( O n w h (A description of the blowdown model used is provided in Reference Q g
6.2.1,4.3 Containment Resporw. Analysis The WGOTillC Computer Code (Reference 1)is used to determine the containment responses following the steam line break.
De containment response analysis is desenbed in subsection 6.2.1.1.
6.2.1.4.3.1 initial Conditions The initial containment conditions are discussed in subsection 6.2.1.1.3.
6.2.1.4.3.2 Slass and Energy Release Data g and M Using References Sg6jas a basis, mass and energy release data are developed to determine
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the containment pressure temperature response for the spectrum of breaks analyzed.
Tables 6.2.1.4 2 and 6.2.1.4 3 provide the mass and energy release data for the cases that produce the highest cor:tainment pressure and temperature in the containment response analysis. Table 6.2.1.4-4 provides plant data used for the cases used in the mass and energy releases determination.
The rate cf startup feedwater addition represents the maximum now rate limited by a casitating venturi to a fully depressurized steam generator. Actual isolation is dependent on signals generated by the protection and safety monitoring system. Feedwater isolation for the split breaks is based on the time required to reach the containment pressure setpoint that generates the isolation signal. De feedwater now rates befare automatic isolation assumed Resision: 14 June 27,1997 6.2 16 3 W85tlngh0US8
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Reofacement insert for SSAR Section 6.2.1.4.2 The steamline blowdown is calculated with the AP600 version of LOFTRAN (Ref. 31).
1 This is a version of LOFTRAN (Ref. 6) which has been modified '> include simulation of the AP600 passive residual heat removal heat exenanger, core makeup tanks, and associated protection and safety monitoring system actuatiollogic. Documentation of the code changes for the passive models,he h:r. d"'ted ! nc M"O (":1. 01).
The methodology for the steamline break analysis is based on Ref. 5.
l
' A prev,de.ck,%
Re 4 e t eau. 'M.
References (No chanae to Ref. 6: Ref. 5 exoanded and Ref. 31 added)
S.
Land, R. E.," Mass and Energy Releases Following a Steam Line Rupture,"
WCAP 8822 (Proprietary) and WCAP 8860 (Non Proprietary), September 1976;
" Supplement 1 Calculations of Steam Superheat in Mass / Energy Releases Following a Steamline Rupture,' WCAP 8822 P S1 (Proprietary), January 1985;
" Supplement 2 Impact of Steam Superheat in Mass / Energy Releases Following a Steamline Rupture for Dry and Subatmospheric Containment Designs,"
WCAP 8822 S2 P A (Proprietary), September 1986.
6.
Burnett, T. W. T.,"LOFTRAN Code Description," WCAP 7907 P A (Proprietary) and WCAP 7907 A (Non Proprietary), June 1984.
^
31.
Carlin, E. L. and U. Bachrach,"LOFTRAN and LOFTTR2 AP600 Code App'icability Document," WCAP 14234, Revision 1 (Proprietary), June 1997.
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- 6. Ergir.etted Safety Sptems
)
1 6.2.5.2.3 Component Description ne system pressuriution equipment is temporanly Wtalled for Type A testing. In addition to one or more compressors, this hardware includes components such as aftercoolets, moisture separators, filters and alt dryers. De hardware characterisucs may vary from test to test.
De flow control valve in the pressuriution line is a leaktight valve capable of throttling to a low Dow rate.
6.2.5.2.4 Instrumentation Applications For Type A testing, instruments are provided to measure containment absolute pressure, dry bulb terr.perature, dew point temperature, air now rate, and atmospheric pressure. Data acquisition equipment scans, processes and records data frorn the individual sensors. For Type B and C tesung, instruments are provided to measure pressure, dry b'ilb temperature, and flow rate.
De quantity and location of Type A instrumentation and permanently installed Type B instrumentation,is indicated on Figure 6.2.51. The type, make and range of test instruments may vary from test to test, ne instrument accuracy must meet the criteria of Reference 13.
6.2.5.3 Safety Evaluation I
ne containment leak rate test system hu no safety related function, other than containment isolation and therefore requires no nuclear safety evaluation, other than containment isolation which is described in subsection 6.2.3.
6.2.5.4 Inservice Inspection / Inservice Testing nere are no special inspection or testing requirements for the containment leak rate test system. Test equipment is inspected and instruments are calibrated in accordance with ANSI.56.8 criteria and the requirements of the test procedure.
6.2.6 Combined License information for Containment Leak Rate Testing The Combined License applicant is responsible for developing a
- Containment Leakage Rrte Testing Program" which willidentify which Option is to be implemented under 10 CFR 50, Appendix J. Option A defines a prescriptive based testing approach whereas option B defines a performance based testing program.
{
6.2,7 References k
- lce Condenser Containment Pressure Transient Analysis Methods," WC AP 8077, March, 1973 (Proprietary), WCAP 8078 (Non Proprietary).
Revision: 15 August 8,1997 6.2 59A W Westingh0088
==
9 3.
,-y-y-
g-.-
w w,--w-
,.-w
i 6, Engineered Safety Feat:res 3.
Shepard, R. M., et al., " Westinghouse Mass and Energy Release Data for Containment Design," WCAP 8264 P A, June 1975 (Propnetary), and WCAP 8312 A, Revision 2.
August 1975 (Non Proprietary).
4.
" Westinghouse LOCA Mass and Energy Release Model for containment Design hi ;h gg g 1979 Version," WCAP 10325, May 1983 (Propnetary).
Land, R. E.,' Mass and Energy Releases Following A Steam Line Rupture," WCAP 88h 5.
g ptcy de.d m (Proprietary) a;id WCAP 8860 (Non Proprietary), September 1976.
mMM b 6.
Ilumett, T. W. T., "LOFTRAN Code Description," WCAP 7997 P A (Proprietary) and Nb"b 4'7 WCAP 7907.A (Non Proprietary), June 1984.
7.
10 CFR 50.46, " Acceptance Cnteria for Emergency Core Cooling Syst,:ms for Light.
Water Cooled Nuclear Power Reactors," and Appendix K to 10 CFR 50, "ECCS Evaluation Model."
8.
liranch Technical Position CSil6-1, " Minimum Containment Pressure Model for PWR ECCS Performance Evaluation."
9.
Bajorek, S.M., et al. " Code Qualification Document for Best Estimate Analysis "
WCAP 12945 P, Revision 1 (Proprietary).
- 10. Fletcher, W.D, Bell, M.J., and Picone, L.F., " Post LOCA Ilydrogen Generation in PWR Containments," Muckatltchnology 10, pp 420-427,1971.
I1. Zittel, H.E., and Row, T ll., " Radiation and Thennal Stability of Spray Solutions,"
Nudcar Tecimelecy 10, pp 436-443,1971.
- 12. Allen, A.O.,Ihc Radiation Chemistry of WattundAquteus Solu.tinm, Princeton, N.J.,
Van Nostrand,1961.
- 13. ANSI /ANS 56.81994, " Containment System Leaks,e Testmg Requirements."
- 14. 10 CFR 50, Appendix J (Draft Proposed Revision), " Containment Leak Rate Testing,"
January 10,1992.
- 15. ' Thomas C. L. Catalvtic Procenes and Proven Catalysts, Academic Press,1970,
- 17. J. Rohde, et al., " Hydrogen Mitigation by Catalytic Recombiners and Ignition During Severe Accidents," Third Intemational Conference on Containment Design and Operation, Canadian Nuclear Society, Toronto, Ontario, October 19 21, 1994.
- 18. J. C. DeVine, Jr. " Passive Autocatalytic Recombiners for Combustible Gas Control in ALWR's," to Mr. James Wilson, Apnl 8,1993.
Revision: 15 3 Westingh0US8 6.2 59B August 8,1997
!jp=Wi-l
- 6. Enslaeered safety Fcit:res
'M -
i
- 19. EPRI Repon, "NIS passive autocatalytic recombiner Depienon Rate Equation for Evaluation of flydrogen Recombination During AP600 Design Basis Accident" EPRI ALWR Program November 15,1995.
- 20. WCAP.I4407(Proprietary)andWCAP 14408(Non Proprietary)WGOTillC Application to AP600," Revision 1 July 1997.
i
- 21. EPRI Repon.
- Evaluation of Quality Assurance Applied to Battelle Tests of NIS Passive Autocatalytic Recombiner," EPRI ALWR Program October 1995.
- 22. NUREO.737, "Clari0 cation of TMI Action Plan Requirements," October,1980
- 23. NUREO.718. Rev. 2. " Licensing Requirements for Pending Applications for Construction Permits and Manufacturing License " January,1982.
- 24. ANSI /ASCE.8 90, Specincation for the Design of Cold Formed Stainless Steel Structural Members
- 25. NUREO-0800, Section 6.2.1.1.A, "PWR Dry Containments, including Subatmospheric Containments."
- 26. "AP600 Accident Analyses Evaluation Models," WCAP.14601, Revision 1 (Proprietary).
I
- 27. Thomas T. Manen, "AP600 Use of Passive Autocatalytic Recombiners (PARS) for l
Design Basis liydrogen Control" to Mr. Nicholas Liparulo April 1,1997.
I I
28 EPRI Repon "The Eficcis of Inhibitors and Poisons on the Performance of Passive I
Autocatalytic Recombiners for Combustible Gas Control in ALWRs," May 22,1997.
1 I
Autocatalytic Recombiners (PARS) for Combustible Gas Control in Nuclear Power l
Plants," June 1997.
I i
- 30. Nuclear Energy Institute Report, NEl 94 01,
- Industry Guidelines for Implementing i
Performance Based Option of 10 CFR 50, Appendit J." Revision 0.
Add Ed.(e4 tout 'M prbo AAA a markq b '6eck (o.2..t A,7.
Y
- DCP/tdC.12NT, B. A. Mc.%ge b T R,Gu.o y, NSAR (g.2.
32, hWky M Ewdunb MoA.s0. Changes,"
9
- Revision: 15 August 8,1997 6.2 60B T Westinghouse
- 6. Engineered Safety Features Table 6.2.1.1 1
- tTMMARY OF CALCULATED PRESSURES AND TEMPERATURES Peak Peak Pressere Available' Temperature Break (psig)
Margie (psi)
('F)
I Double-ended hot leg guillotine R9 J7, 7 kr G.4 190r 3 99, 5 l
Double ended cold les guillotine
- 44 W. S M O. 's 280-r c W E
'}
F l
4468-M.M1 DER.102% power.
4H #3 7 1 4 /. J 156+ 5 O ' b MSIV failule F
l 4.3*" M.tull DER. 30% poww.
4@ W.Y WO (,
14H 3 S 4 * '#
MSIV failure 1.
Design Pressure is 45 psis Revidos: 13 May 30,1997 6.2 60 3 Westingbotse l
yaNI
- 6. En Inen OpyO DELETE % b\\t lo.l.\\A-4 h%3L
(,.2.\\.\\-1
'able fr..
(S i of 6)
METAI, llEAT SINKS hfetallic Esposed Area fleuription
( f t')
1hltkhess tit)
Staterial Pal t Reactor Cailt+
Miwellaneous Equipment and Sinactural Steel 21149 0 083 SS None 62 06 0 002 CS CZ 2l19.7 0 007$6 S
CZ+E 104 0 0 00870 C5 0
27$3 0 012 CS O
9H6 7 0166 CS CZ+E Arrumulator Cailty Southeast Miwellaneous Equipment and Structural $icci 767.7 0 166 CS CZ 23N 2 0 007.46 CS CZ+E 104 $4 0 0124 CS t,
Accumulator Catity (Northeast) hinwellaneous Equipment and Structural Steel 767.7 0.166 CS CZ 3360 4 0 00756 CS CZ+E Steam Generator Room East hinwellaneous Equipment and Structural teci 2240 10 0 0:430 CS CZ+E 33h8 77 0 (x)756 CS CZ+E IN $4 0 0120 >
CS O
181.39 0 INno CS CZ+E 281.03 0 405(E)
CS CZ+E Steam Genera.or un West htiweltaneous E ipment ar'd Structural Steel 2240 10 0 02430 CS CZ+E 33R8 77 0 (K)756 CS CZ+E 104 54 0 01200 CS G
181.39 0 IN00 CS CZ+E 28103 0 4050()
CS CZ+E Revision: 14 W Westinghouse 6.2 63 June 27,1997 i
l
- 6. Engineered Stfety Fe tures Td.!: 6.2.1.1-4 (Sheet 2 of 61 METAL, llEAT SINKS hietallic Esposed Description Area (ft ) Thickness (fu Ma al Paint 8
'.:Vi & CMT Room Miscellaneous Equipment and Structural Steel 79.72 0 6(KKX)
SD None i
480.86 0 73700 '
SS None 114 67 0 75( )
SS None 1449.32 0 3620 CS CZ+E 1252.95 0 41700 CS CZ+E 1262.14 0 08330 CS CZ+F 3
520 2 0 25000 CS CZ+E I ' 6.66 0 03756 CS CZ+E 505.$0 0 00870 CS G
1848.80 0 44500 CS CZ+E l1063 75 0.13542 CS CZ+E 3285.94 0 03250 CS CZ+E 7563.38 0.03860 CS CZ+E 436 92 0.01632 CS CZ+E 321.80 0.17500 CS CZ+E
'495L44 0 01100 CS CZ+E 320.15 0 01200 CS G
43(M 0 01386 CS G
Refueling Room i
Macellaneous F uipment and Structural Steel 933 8 0 (M200 SS None 79 48 0 36660 SS None 2016 (X) 0.05830 SS None 279 83 0 00756 CS CZ+E tR ST Room acellaneous Equipm'ent and Structural Steel 7050.96 0 05000 SS None 1
Revision: 14
[1
~
June 27,1997 6.2-64 W W85tingh00S8
- 6. Engineered Safety F ct:res Table 6.2.1.14 (Sheet 3 of 6)
METAL llEAT SINKS 4
Metallic.
Fsposed Area Dewrlption (ft')
Thickness (ft) Material alnt Upper East SG Compartment Miscellaneous Equipmet.: and Structural Steel 77.39 0.37700 CS C7+E 103.67 0.37500 f'S CZ+E 5612.9 0 00756 CS CZ+E Upper West SG Compartment Miscellaneous Equipment and Structural Steel 103 67.
0375 CS CZ+E 5612.9 0 1756 CS CZ+E 77.39 0 37700 CS CZ+E South inner Half Annulus Miscellaneous Equipment aiid Structural Steel 4ct 0 02100 SS None l
7 b0 0.05520 CS CZ+E 457.70 0 00756 CS CZ+E Eouth Inner Quarter Annulus Miscellaneous Equipment and Structural Stee 819 80 0 05520 CS CZ+E J
North inner Half Annulus Miscellaneous Equipment and Structu teel 607.26 0 01:00 CS G
I47.60 0 00756 CS CZ+E North inner Half Annulus Misce!!aneous Equipment nd Structural Steel 3987.82 0 00756 C5 CZ+E 399 95 0 01200 CS G
North Mid Quart /r Annulus Miscellaneous uipment and Structural Steel 540 71 0 01632 CS CZ+E 356 68 0 06700 CS CZ+E 888.90 0 00756 CS CZ+E f
241.18 0.01947 CS CZ+E 788.80 0.00870 CS G
494 90 0.13000 CS CZ+E Revision: 14
[ W8Stingfl0088 6.2 65 June 27,1997 v..
fi y
I
- 6. E sinected Satty Fe:tures Table 6.2.1.14 (Sheet J jf 6)
METAL HEAT Sti S
\\
Metallic Exposed llescription Area tft )
Thkkness (ft)
Material Paint I
a West Mid Quarter Annulus
)
Miscellaneous Equipment and Structural Steel 491.60 0 02100 None 3442.0 0 00756 CS CZ+E 136.80 0 01:00 CS G
20*f '5 0.0418 CS CZ+E 700.28 0( 00 CS CZ+E 356 68 06700 CS CZ 265 90 0 ON00 CS CZ+E 788 80 0 00870 CS G
494.
0.13000 CS CZ+F South Mid Quarter Annulus Miscellaneous Equipment and Structural Steel 356.68 0 % 700 CS CZ+E 3783.0 0.00756 CS
'CZ+E 788.80 0 00870 CS G
494.90 0 13000 CS CZ+E 2N.75 O N180 CS CZ+E 700 28 00N00 CS CZ+E 356.68 0 06700 CS CZ+E East Mid Quarter Annul Miscellaneous Equipmer nd Structural Steel 265.90 0 00400 CS CZ+E 788 80 -
0 00870 CS G
494 90 0.13000 CS CZ+E North Outer rter Annulus Miscellane s Equipment and Structural Steel 1032 4 0 00756 CS CZ+E 402.10 0 07000 CS CZ+E 788.80 0 00870 CS CZ+E
/
1101.60 0.13000 CS CZ+E
=
Revision: 14 June 27,1997 6.2-66 y Westingh0USS
- 6. Engineered Safety Features Table 6.2.1.14 (Sheet 5 of 61 METAL IIEAT SINKS Sletallie Esposed Description Area tit')
Thickness tft)
Staterial / Paint West Guter Quarter Annulus Miwellaneous Equipment and Structural Steel 1648 85 0 00736 bS CZ+E 402.10 0 070(0 CS CZ+E 788 80 0 0087V' CS G
/
1101.60 0 15000 CE CZ+E South Outer Quarter Annulus Miscellaneous Equipment and Structural Steel 1099.2 0 00756 CS CZ+E 40 0 07000 CS CZ+E 788 80 0 00870 CS G
I101.60 0 13000 CS CZ+E East Outer Quarter Annulus 6!5,2 0.22000 CS CZ+E
/
402,10 0 07(00 CS CZ+E 824.50 0 00756 CS CZ+E 788.80 0 00870 CS G
1101.60 0 13000 CS CZ+E j
East Quarter Inner Don)r#
Miscellaneous Equipngnt and Structural Steel 1996 00 0.14500 CS CZ7 North Quarter Inn /
er Dome Miscellaneous uipment and Structural Steel 1996.00 0.14500 CS CZ+E Revision: 14
[ W85tingh00$8 6.2-67 June 27,1997
- 6. E:gineered Saf;ty l'est:res Table 6.2.1.14 (Sheet 6 of 6)
METAL IIEAT SINKS
/
Metallic Esposed
/
Description Area (ft )
Thickness (ft)
Matestal Paint 8
West Quarter Inner Dome j/
Miscellaneous Equipment and Structural Steel 1996 00 0.14500, /
CS CZ+E East Quarter Inner Dome Miscellaneous Equipmsnt and Structural Steel 1996 00 14500 CS CZ+E 1,ower Chimney 145411 0 01990 CS CZ+E Miscellaneous Equipment and Structural Steel 277.5 0.02250 CS CZ+E
/
d) 24 0 01200 CS G
142.11 0 00'156 CS CZ+E 78 93 0 in)756 CS CZ+E Notes:
1 Two types of materials will be used for metallic structures:
B. Stainless Steel (SS)
- 2. Three paint coatings are usc46n metallic structures:
B. Carbo Zine (CD j/
A Epoxy (E)
D. Iloi dipped galvapfeing (G)
Revision: 14 June 27,1997 6.2 68 T L m 7,.iouse
- 6. Engineered Safety Fe:t:res Table 6.2.1.15 (Sheet I of 3)
CONCRETE IIEAT 5ttiXS
,/
l.iner Plate Paint Exposed Area Thickness Surface (ft')
(ft)
Interior Exterior Interior I;. terior Reactor Cavity Structural malls Doors und 219.50 3.260 CS CS CZ+'
CZ+E ceilings 693 00 8 890 CS CS
~j
+E CZ+E IM4 28 4 000 CS CS CZ+E CZ+E 976.7 6 460 CS CS CZ+E CZ+E 214.50 2.500 CS C
CZ+E CZ+E 2429 00 12.520 CS CZ+E Accumulator Cavity South East Room Structural walls, noors and 245 46 4 000 Cr SS CZ+E None ceilings 718 50 2.000 CS None CZ E
2118 55 12.520 CS CZ+E Accumulator Casily North East koom Structural walls, noors and 375 10
/ 4.500 CS None CZ+E E
ce!!ings
/
993 00 2.000 CS None CZ+E E
2816.
12.520 CS CZ+E Steam Generator Room East Structural walls, floors and 2970.37 2 500 CS CS CZ+E CZ+E ceilings 752.16 4 000 CS SS CZ+E None 941.44 12 520 CS E
West Structural wal, noors and 2333.7 2.500 CS CS CZ+E CZ+E ceilings 758 16 4.000 CS SS CZ+E None 1986 6 12.520 CS C7+E Revision: 14
[ W65thgh0Use 6.2-69 June 27,1997
- U(
- 6. E gl. tred S-f;ty Fe:tures Table 6.2.1.1 $ (Sheet 2 of 3)
CONCRETE IIEAT SINKS 1.iner Plate Paint [
Exposed Area Thickness
/
Surface (ft')
(ft)
Interior Exterior Interiv Exterior CMT and CVS Room Structural walls, noors and 2550.78 2.500 CS None CZ E
ceilings 1630 00 4.000 CS SS CZ+E None 5109 33 1.125 CS N ie CZ E
346 46 2.000 CS CS CZ CZ 5161.52 12.520 None E
Refueling Room Structural walls, doors and 776 37 1,420 None ceilings 1705.99 4.000 SS SS None None 1539 00 12.52 SS None IRWST Room Structural walls, Doors and 3146.36 2000 SS None None E
ceilings 3585 20 12.520 SS None Upper East SG Compartment
[
Structural wall, Goors and l' 1 "
'500 CS CS CZ+E CZ+E ceilings Upper West SG Compartment Structural walls, noors a 1241.22 2 500 CS CS CZ+E CZ+E ceilings South inner IIalf A ulus Structural walls, rs and 491 66 2.000 SS SS None None ceilings Inner Half nulus Structural, alls, Goors and 1281.38 2.500 CS CS CZ+E CZ+E ceilings,/
/
Retision: 14 June 27,1997 6.2-70
[ Westingh00S8
- 6. Engineered Safety Itt:res Table 6.2.1.15 (Sheet 3 of 3)
CONCRETE IIEAT SINKS
/
l.iner Plate
,/Paln' Exposed Area Thickness
/
3 Sutface (ft)
(ft)
Interior Exterior -Interior Exterior North Inner llalf Annulus Structural walls, ceihngs, 1005.00 2 500 CS CZ+E CZ+E and Doors West Mid Quarter Annulus Structural wallt, ceilings.
491.66 2.000 S
SS None None andflonrs Air llaffle & Shield llullding fewer Gap Structural walls, ceilings, 53065.02 3.
.fone None and Doors Lower Chimney Structural walls, ceilings, 13357.18 0.500 None None None None and Doors 1397p6 2.000 None None None Nonc 1272.00 1.000 None None None None Top Chimney Structural vslls. ceilings, 2161.40 2.000 None None None None and Doors d's.g3:
1.
Steel liner plates ar/cither:
A.
II. Stainless S iel (SS)
J 2.
Paint on knerplates and concrete surfaces o either:
A.
Epoxy (!!)
B. Cartxy'/anc (CZ)
When Carbo Zine and Epoxy r.re used together, the Carbo Zine is applied as a primer, then the Eposy is applied'as a topco.it.
/
/
Revision: 14
[ W6Silngh0USe 6.2 71 June 27,1997
- n:
i
]i
- 6. Eigineered Sifaty Fc"tures Table 6.2.1.16 CONTAINMENT SIIELL AND BAFFLE METAL IIEAT SINKS l
Exposed Thickness Area Ift')
(ft)
.\\taterial Paint Stack #1 Shell 11266.6 0.13641 CS CZ Baf0e 10653.7 0.00839 CS CZ Stack #2 She:I i1266.6 0.1364 CS CZ Bafne 10653.7 0.
39 CS CZ Stack #3 Shell i1266.6 0.1364i CS CZ Baffle 10653.7 0.00839 CS CZ Stack #4 Shell 11266.6 0.13641 CS CZ Baffle 1065 0 00839 CS CZ Stack #5 Shell
.128.9 0.13641 CS CZ Bafne l 183.9 0.00839 CS CZ Stack #6 Shell 2128.9 0.13641 CS CZ Bafne 1183.9 0.00839 CS CZ Stack #7 Shell 2128.9 0.13641 CS CZ Bafne
! ! 83.9 0.00839 CS CZ Stack #8 Shell 2128.9 0.1364i CS CZ Baf0e
!I83.9 0.00839 CS CZ Revision: 14 June 27,1997 6.2-72
[ Westingh00Se j
- 6. Engineered Safety Feat ~res Table 6.2.1.17 SillELD BUILDING CONCRETE IIEAT SINKS
/
Exposed Area (ft')
1hickness (ft)
Material Paint Stack #1 Shield Bldg.
12057.5 3.0 Concrete None Stack #2 Shield Bldg.
12057.5 3.0 Co rete None Stack #3 Shield Bldg.
12057.5 3.0 Concrete None Stack #4 Shield Bldg.
12057.5 3.0 Concrete None Stack #5 Shield Bldg.
2497.5
.0 Concrete None Stack #6 Shield Bldg.
2497.5 3.0 Concrete None Stack #7 Shield Bldg.
2497.
3.0 Concrete None Stack #8 Shield Bldg.
2497.5 3.0 Concrete None
/
,/
/
Revision: 14 W85tingt10US8 6.2-73 June 27,1997
- 6. Engineered Safety Features 1
Table 6.2.1.l 8 PIIYSICAL PROPERTIES OF PASSIVE IIEAT SINKS Thermal Density Cond sctivity Specific Heat Dry Wet
.\\laterial (lbm/fe. )
(Btwhr.ft.'f)
(Bru/lbm.'F)
Emis.
Emis.
Epoxy 105 0.1875 0.35 0.81 0.95 l
Carbon Steel 490.7 23.6 0.107 0.81 0.95 Concrete 140.
0.83 0.19 0.81 0.95 Stainless Steel
- 501, 9.4 0.12 0.81 0.95 Carbo Zinc 207.5 1.21 0 15 0.81 0.95 Oxidized Carbo Zinc 207.5 0302 0.15 0.81 0.95 l
Carbo Zinc.PCS 207.5 0.302 0.15 le.10 le.10 I
inside Surface A:r e O F---.. MG'L o.0'3I
. A'40 le-lo A e - t o..
A : e.2 E o #F.
- o. os'&
- o. oI9 L o.242.
. I e-to le -to Are EjeQF _ 094H
.0, 0hK' O. 2AS- -
! e -19 ie -t o Revision: 13
[ W8Stiflgh00$4 6.2-81 May 30,1997
- 6. Itgineered Safety Fe:t:res Table 6.2.1.3 9 (Sheet 4 of 5)
LONG TERM DECLG BREAK POST BLOWDOWN MASS AND ENTilALPY RELEASES Time Slass Enthalpy Stass Enthclpy (sec)
(thnVsec)
(Htu/!bm)
(Ibm /sec)
(Btw1bm) 524.64 58.96 380.28 120.27 1167.40 544.64 60.92 374.34 I l 7.19 1167.40 564.64 62.77 368.65 I i4.23 1:57.40 584.64 64.52 363.17 Ii1.37 1167.40 6N.64 66.I7 357.91 108.61 1167.40 654.64 69.55 345.88 102.43 1167.40 704.64 72.42 334.73 96.78 1i67.40 754.64 74.81 324.37 91.60 1167.40 804.M 76.79 314.65 86.84 l l67.40 854.64 78 24 305.69 82.60 I167.40 9 N.64 79.36 297.25 78.70 116*l.40 954.64 80.20 289.27 75.09 I I67.40 1004.64 80.74 281,76 71.76 I I67.40
~~
1504.75 223.22 149.04 47.I2 1167.40 2004.75 211.76 127.84 37.58 1167.40 35N.75 156.70 l(M.74 27.09 l 167.40 40(M.75 157.03 100.94 25.08 1167.40 6004.84 153.75 96.34 21.54 I I67.40 7504.95 134.76 96.64 20.33 1167.40 8004.95 132.I4 96.53 19.75 i I67.40 10005.00 128.76 96.I8 I8.53 1167.40 15005.00 130.22 95.25 16.6I I I67.40 20005.80 114.62 95.62 15.38 I I 67.40 26007.30
% 35.%
96ty til.G2-14.64 1167.40 30007.90 AM O. 0 leNHe ll(.t.%
t#-ft I6 32.
t+6940 M%.30
{ 0 00 36008.10 0.00 l 168.30 15.38 l 168.30 40(XX).00 1168.30 14.76 l 168.30 60(XX).00 0 00 1168.30 13.20 1168.30 L
Revision: 14
[ WeStingh00S8 5.2 99 June 27,1997
- 6. Engineered Saf;ty Ittures Table 6.2.1.3-9 (Sheet 5 of 5)
I,0NG. TERM DECLG IIREAK l'OST ill,0WDOWN MASS AND ENTIIAI,l'Y REI. EASES Time
.\\ tass Enthalpy Mass Enthalpy (sec)
(Ibm /sec)
(!!tu/lbm)
(ibm /sec)
(litu/lbm) 8(XX)0 00 1168.30 12.19 1168.30 l(XXXX) 00 0.00 1168.30 11.42 1168.30 15(XXX).<X) 0.00 I l68.30 10.10 1168 30 2(XXXX) 00 0.00 1168 Y 9.20 1168.30 400(XX).00 0(X) i1-
- 7. I 5 I I68.30 6(XXXX).00 0 00
,J 6.07 1168.30 8(XXXX).00 0.00 1 ea.30 5.38 I I68.30 l(XXXXX) 00 0 00 1168.30 4.89 1168.30 150(XXX).00 0.00 1168.30 4.11 I I 68.30 2(XXXXX).Or' O.00 1168.30 3.62 II68.30 4000000.00 1168.30 2.57 I i68.30 Resision: 14 June 27,1997
[ Westiflgh0US8 6.2-100
- 6. Engineered Sofety Features l'
Table 6.2.1.4 2 (Sheet I of 8)
StASS AND ENTilALPY RELEASE DATA FOR TIIE CASE OF h!AIN STEAh! LINE FULL DOUBLE ENDED RUPTURE FROh! 30% POWER LEVEL WITl! FAULTED LOOP h!AIN STEAh! LINE ISOLATION VALVE FAILURE TIIAT P
DUCEllilGIIEST CONTAINMEXQRESSURE M.w in d stm nu 6.*L, l ewdew.V it Initial steamfeherator mass ( lbm )
t6HM-l(A G 'O Mass addedpy feedwater tiashing ( lbm )
- 4493 IC Vf O I
Mus added,....~l...U.. _ _.x ( lbm )
969-T9'7C l
Initial steam pressure ( psia )
. W5-6 9 '7 0. 83 i
Feedwater line isolation at ( sec )
- MG-7.91 l
Steam line isolation at ( sec )
- M9-7. D Time (sec)
Mass (Ibmhee)
Enthalpy (Bru/lbm)
I
~
00 0 00
',g 00 0.1 12438.1 1193.58 4
3 ek 1
0.2 12412.4 1193 65 l
0.3 12392.9 1193.71 b2 O
l 0.4 12373.5 1193.76
-C l
0.5 12354.8 1193.81
(
l 0.6 12336.5 1193.86 i,
1 07 12318.5 1193.91 1
0.8 12300.9 1193.95 l
0.9 12283.7 1194.00 l
1.0 12266.8 1194.04 1
1.1 I2250.1 1194.08 1
1.2 5397.5 3.94 l
1.3 5353.1 1194.22 l
1.7 13.8 1195.06 l
2 5084.4 1195.81 1
2.5 4964.0 1196.49 l
2.9 4850.3 1197.11 l
3.3 4743.I i197.67 1
3.7 4642.6 1198.19
/
//
I 4.1 4546.9 1198.67 LL t
Revision: 13 May 30,1997 6.2 104 3 Westingflouse
TIME MASS ENTHALPY-(sec)
(t>rtVsec) - (BTU / Ibm)
E 0.0 12575 1193 0.1 12575 1193 0.2 12547 1193
%dD 0.3 12525 1193
/
(I 0.4 12503 1193 0.5 12483 1193 O.6 12462 1193 i
0.7 12442 1193 0.8 12423 1193 0.9 12404 1193 1.0 12385 1193 4
l 1.1 5667 1194 1.2 5621 1194 1.3 5584 1194 1.4 5547 1195 l
1.5 5511 1195 1.6 5475 1:95 1.7 5440 1195 1.8 5405 1195 1.9 5371 1196 2.0 5337 1196 2.1 5305 1196 2.2 5272 1196 2.3 5241 1196 2.4 5210 1196 2.5 5179 1107 2.6
-5149 1197 2.7 5119 1197 4
2.8 5089 1197 2.9 5060 1197 3.0 5032 1197 3.1 0004 1198 3.2 4975 1198-3.3 4948 1198 3.4 4921 1198 3.5 4894 1198 3.6 4868 1198 3.7 4843 1198 3.8 4818 1108 3.9 4792 1198 4.0 4767-1199 4.1 4743 1199 4.2 4719 1199 4.3 4696 1199 4.4 4673 1199 4.5 4650 1199 4,6.
4628
.1199 4.7 --
4606 1199 4.8 d584 1199 4.9 4562 1199
5.0 4542 1200 5.1 4520 1200 5.2 4500 1200 5.3 4480 1200 5.4 4459 1200 5.5 4439 1200 5.6 4421 1200
$gg g' 4
5.7 4401 1200 5.8 4382 1200
/
.. j tb, 5.9 4363 1200 V
6.0 4344 1200 c
6.1 4326 1200 6.2 4308 1200 6.3 -
4291 1201 6.4 4273 1201 6.5 4256 1201 6.6 4238 1201 6.7 4222 1201 6.8 4205 1201 6.9 4189 1201 7.0 4172 1201 7.1 4156 1201 7.2 4140 1201 7.3 4125 1201 7,4 4109 1201 7.5 4094 1201 7.6 4079 1201 7.7 4065 1201 7.8 4049 1201 7.9 4036 II 8.0 4021 1201 8.1 4007 1202 8.2 3997 1202 8.3 3984 1202 8.4 3973 1202 8.5 3962 1202 8.6 3950 1202 8.7 3940 1202 8.8 3929 1202 8.9 3918 1202 9.0 3907 1202 9.1 1872 1203 9.2 1868 1203 9.3 1864 1203 9.4 1860 1203 9.5 1856 1203 9.6 1852 1203 9.7 1848 1203 9.8 1844-1203 J
9.9 1840 1203 10 1836 1203 l
11 1796 1203 1
12 1757 1203 13 1718 1204 i
=..
~
14 1679 1204 15 1639 1204 16 1601 1204 17 1561 1204 18 1517 1204 19 1470 1204 20 1422 1204 21 1385 1204 T"ggd 50
~~
22 1340 1204 s
23 1295 1204 y) 13 }
24 1252 1204 25 1211 1204 26 1171 1204 27 1133 1204 28 1097 1204 29 1062.
1204 30 1029 1204 31 998 1204 32 968 1203 33 939 1203 34 912 1203 35 888 1203 36 866 1203 37 845 1202 38 824 1202 39 805 1202 40 786 1202 41 768 1201 42 751 1201 43 735 1201 44 719 1201 45 704 1201 46 689 1200 47 676 1200 48 662 1200 49 650 1200 50 637 1199 55 584-1198 60 541 1197 65 508 1196 70 481 1195 75 459 1194 80 442 1194 85 428 1193 90 417 1193 95 408 1192
-100 399 1192 105 392 1192 110 385 1191 115 378 1191 120 372 1191 125 365 1190 130 358 1190 135 351 1190
140 344 1189 145 337 1189 150 330 1189
- 155 324 1188 160 318 1188 165 312 1188 170 306 1187 175 301 1187 Tj.,4 ) AC 180 297 1187 x
(4 ;$ R) 185 292 1186 190 288 1186 195 285 1186 200 281 1186 205 278 1185 210 275 1185 215 272 1185 220 270 1185 225 267 1185 230 265 1185 235 263 1184 240 261 1184 245 259 1184 250 256 1184 255 254 1184 260 252 1184 265 250 1183 270 248 1183 275 246 1183 280 244 1183 285 242 1183 290 240 1183 295 237 1182 30) 235 1182 i
306 233 1182 312 230 1182 318 227 1181 324 225 1181 330 222 1181 336 220 1181 342 218 1181 348 215 1180 354 213 1180 360 211 1180 366 208 1180 372 206 1180 378 204 1179 384 202 1179 390 200 1179 396 198-1179 402 196 1179
- 408 194 1178 414 192 1178 420 190 1178 426 188 1178 s-m m
f 43?
186 1178 438 184 1177 444 183 1177 450 181 1177 456 179 1177 462 177 1177 468 175 1176 474 173 1176 p'-0 d S
- 480 168 1176 qg) 486-163 1175
{6v 492 157 1174 a
498 152 1174 504 145 1173 510 138 1172 516 130 1170 522 118 1168 528 102 1166 534 84 1162 540 63 1156 546 9
1151 552 0
1151 A
9
6 Engineered Safety Features
~
I Table 6.2.1.4 2 (Sheet 2 of 8)
SIASS AND ENTHALPY RELEASE DATA FOR THE CASE OF 51AIN STEAM LINE FULL DOUBLE ENDED RUPTURE FRO 5130c POWER LEVEL WITH FAULTED c
LOOP STAIN STEA51 LINE ISOLATION VALVE FAILURE THAT PRODUCES HIGHEST CONTAINMENT PRESSURE w
/ Time (sec)
Mass (Ibm /sec)
Enthalpy (Btu /lbm) l 4.5 4458.9 1199.10 i
49 4375.6 1199.49 j
l 5.3 4296.8 1199.S6 1
5.7 4222.I 1200.20 1
6.I 4151.3 1:00.52 l
65 4084.3 1 00.81 1
69 4020.7 1:01.08 1
7.3 3960.5 1201.32 1
7.7 3903.3 1:01.55 1
81 3849.1 1201.76 I
8.5 3806.8 1:01.93 i
8.9 3765.0 1:02.09 l
9.3 1815.1 1202.58 9i 1799.8 1202.68 10.I 1784.7 1:02.78 10.5 1769.7 1202.87 10 9 1754.8 1 02.96 11.3 1739.9 1:03.05 l
11.7 1725.I 1203.I4 12.1 1710.2 1203.22 i
12.5 1695.4 1203.31 12.9 1680.5 1203.39 q
I I 3.3 1665.5 1203.46 l 3.7 1650.6 1203.54 i
14 1 1635.7 1203.61 l
14.5 1620.7 1203.69
/
Revision: 13 3 W85tingh0054 6.2 105 May 30,1997
- 6. Fzgineered Sity Features I
Table 6.2.1.44 (Sheet 3 of 8)
MASS AND ENTHALPY RELEASE DATA FOR THE CASE OF MAIN STEAM LDT FULL DOUBLE ENDED RUNURE FROM 30% POWER LEVEL WITH FAULTED LOOP MAIN STEAM LLNE ISOLATION VALVE FAILURE THAT PRODUCES HIGHEST CONTAINMENT PRESSURE a
[ Time (sec)
Mass (Ibm /sec)
Enthalpy (Btu /lbm)'
14.9 1605.8 1203.75 l
l l
15.3 1590.9 1203.82 l
15.7 1576.1 1203.88 I
16.1 1561.3 1203.94 l
I 16.5 1546.5 1204.00 I
f 16.9 1531.1 1204.05 l
17.3 1515.1 12N.it l
17 7 1498.4 -
12N.16 l
18 1 148t.3 12N.21 l
IS 5 1463.8 1204 26 I
i89 1446.0 1204.29 I
19 3 1428.0 12N.33 1
19 7 1409.9 12N 36 20.5 1382.9 1204 40 i
j I
22.5 1295.8 1204.47 I
l 24.5 1213.5 12N 45 l
l 26.5 1137.6 12M34 i
28.5 1067.9 1204.16 l
l 30.5 1004.2 1203 89 I
32.5 946.2 1203.57 l
34.5 893.5 1203.20 1
36.5 845.6 1202.79 I
I 38.5 802.6 1202.35 I
40.5 763.5 1201.90 l
l 42.5 728.0 1201.42 l
44.5 695.5 1200 9 Revision: 13 May 30,1997-6.2 106 3 W65tiflgh00st
l l
~
- 6. E gtneered Saf;ty Features i
Table 6,2.1.4 2 (Sheet 4 of B)
SIASS AND ENTHALPY RELEASE DATA FOR THE CASE OF SIAIN STEAh! LLNE FULL DOUBLE ENDED RUPTURE FROS130% POWER LEVEL WITH FAULTED LOOP S1ALN STEAh! LINE ISOLATION VALVE FAILURE THAT PRODUCES HIGHEST f ONTAINhfENT PRESSURE Enthalpy (Bbg A'imeTre ass (Ibm /sec) y i
46.5 665.7 1200 41 1
48.5 642.8 II99.99 I
50.5 620.9 1199.55 l
52.5 600.6 1199.I2 l
54.5 581.8 1198 69 I
56.5 564.6 1198.28 l'
58.5 54f.7 1197.88 I
1 60.5 534.0 1197.49 I
62.5 520.6 1197.I2 l
l 64.5 508.3 i196.77 I
66.5 497.I i196.44 I
68.5 486.9 1196.13 l
70.5 477.4 1195.83 I
72.5 468.7 1195.54 I
74.5 460.8 1195.27 1
76.5 453.S 1195.01 1
78.5 446.8 1194.77 l
80.5 440.7 1194.54 I
82.5 435.I 1194.32 I
$4.5 429.8 1194.Ii 1
86.5 425.0 1193.92 1
88.5 420.5 1193.73 I
90.5 416.3 1193.56 i
92.5 412.4 1193.39 I
94.5 408.7 1193.23 l
96.5 4M 1 1193.08 Revision: 13 3 WOStingh00s4 6.2 107 Stay 30,1997
- 6. Ecgineered Sciety Features 1
Table 6.2.1.4 2 (Sheet 5 of B)
S1 ASS AND ENTHALPY RELEASE DATA FOR THE CASE OF SIAIN STEASI LINE FULL DOUBLE ENDED RUPTURE FROST 30c POWER LEVEL WITil F AULTED LOOP STAIN STEASt LINE ISOLATION VALVE FAILURE TILAT PRODUCES HIGHEST CONTAINStENT PRESSURE Time (sec)
Mass (Ibm /sec)
Enthalpy (Bru%/lI l
98.5 401.9 1192.94 I
l01.0 398.3 1192.77 l
l 105.0 392.3 1192.50 l
l 109.0 386.5 1192.23 1
113 0 380.9 1191.98. x
, - l lit.71 I
i17 0 375.4 1
121 0 369.9 1191 45 l
125 0 364.3 1191.I8 I
I29 0 358.8 1190.90 l
133 0 353.2 1190.62 l
I37 0 347.6 1190.34 I
i 141 0 342.2 1190.05 l
I45.0 336.8 1189.76 l
l 149 0 331.4 1189.47 l
153 0 326.2 1189.19 l
157 0 321.2 1188.91 161.0 316.3 1188.63 165.0 311.6 1188.36 169.0 307.1 1188.10 I73.0 302.8 1187.85 177.0 298.7 1187.61 181.0 294.9 1187.38 I
185 0 291.2 1187.I6 I
I89 0 288.0' II86.%
193.0 284 9 1186.77 l
197.0 282.1 1186.58 v
Revision: 13 Stay 30,1997 6.2 108 3 W65tinghouS6
- 6. Englaeered Safety Features I
Table 6.2.1.4 2 (Sheet 6 of 8)
StASS AND ENTHALPY RELEASE DATA FOR THE CASE OF 51AIN STEAh! LINE FULL DOUBLE ENDED RUMURE FROST 30% POWER LEVEL WITH FAULTED LOOP STAIN STEA51 LINE ISOLATION VALVE FAILURE THAT PRODUCES HIGHEST CONTAIN5fENT PRESSURE j
Time (sec)
Slass (Ibrdsec) y I
201.0 279.4 1186.4I l
205.0 276.9 1186.24 I
209.0 274.5 1186.08 l
213.0 272.3 1185.93 1
217.0 270.I 1185,78 1
221.0 268.1 1185.64 1
225.0 2661 1185.50 1
229 0 264.2 1185.36 l
233.0 262.4 1185.23 1
237.0 260 6 I I85.10 I
241.0 258.8 1184.97 I
245 0 257.1 1184.84 l
249 0 255.4 1184.7I I
253.0 253.7 I I84.59 I
257 0 25 2.0 1184.45 1
261.0 250.3 1184.32 f
265 0 248.6 1184.19 269.0 246.9 1184.06 273.0 245.2 1183.92 i
277.0 243 4 1183.78 f6 281.0 241.7 i I83.64 I
285.0 239.9 1183.50 1
289 0 238.2 1183.35 1
293 0 236 4
!!83.21 1
297.0 234 6 1183.06 1
301.5 232.8 1182.
s Revision: 13
[ Westinghoust 6.2 109 Stay 30,1997
- 6. E:gineered Saf:ty Features 1
l Table 6.2.1.4 2 (Sheet 7 of 8)
StASS AND ENTHALPY RELEASE DATA FOR THE CASE OF SIAIN STEAM LINE FULL DOUBLE ENDED RUPTURE FROST 30'4 POWER LEVEL WITH FAULTED LOOP STAIN STEASI LINE ISOLATION VALVE FAILURE THAT PRODUCES HIGHEST CONTAINSIENT PRESSURE
, - ~
Time (sec)
Stass (Ibm /sec)
Enti.alpy (Btu 1bm) s 307.5 230.2 1182.68 i
l 313.5 227.5 1182.45 I
319.5 224.9 1182.22 f
i 325.5 222.4 1181.99 I
331.5 219.9 11L1.77 i
337.5 217.4 1181.54 1
343.5 215.0 1181,32 1
349.5 212.6 1181.10 I
355.5 210.3 1180.88 l
361.5 208.0 1180.67
\\
l 367.5 205.8 1180 46 i
l 373.5 203.6 1180.24 f
l 379.5 201.5
!!80.04 i
l 385 5 199.4 1179 83 l
l 391.5 197.3 1179.62 f
l 397.5 195.4 1179.43 I
403.5 193.5 1179.23 l
l 409.5 191.6 1179.N l
415.5 I89.7 1178.85 l
421.5 187.8 1178.65 l
427.5 185.9 1178.46 1
j 433.5 184 0 1178.26 I
439 5 182.2 1178.06 l
445 5 I80.3 1177.85 l
l 451.5 178.4 1177.65
/
l 457.5 176.5 1177.44
/
i Revision: 13 Stay 30,1997 6.2 110
$ WestinghouS6
sa-i
- 6. Engineered Safety Fectures I
Table 6.2.1.4 2 (Sheet 8 of 8) htASS AND ENTHALPY RELEASE DATA FOR THE CASE OF STAIN STEAM LINE FULL DOUBLE ENDED RL7TURE FROh! 30fc POWER LEVEL WITH FAULTED LOOP SIAIN STEAM LINE ISOLATION VALVE FAILURE THAT
_. /
PRODUCES HIGHEST CONTAINMENT PRESSURE
--~---
Time nec)
.\\ tass Obm/sec)
En Ipy (B
)
s I
4635 174.6 1177 23
(
I 469.5 172.6 1177.02 I
i 475.5 170.9 1176.83 1
481.5 169.0 1176.62 l
487.5 166.9 1176.39 l
493 $
165.6 1176.23 1
4995 164.8 1176.14 l
505 5 163.3 1175.98 1
511
- 161.1 1175.72 1
51' 5 158.6 1175.41 I
$23 5 154.7 1174.95 I
529 5 149.5 1174.28 I
535 5 144.1 1173.58 I
541 5 138.6 1172.82 1
547.5 133.0 1172.01 f553.5 I
128.4 1171.14 559 5 121.6 1169.92 1
565.5 113.7 1168.52 571.5 103.7 1166.73 I
577.5 91.6 1164.41 1
583.5 77.5 1161.22 1
589.5 60.5 1156.41 l
595.5 35.2 1151.42 1
601 5 '
O.d 1150.91 I.
\\
607.5 0.0 1150.91 1-g 613.5 0.0 1150.91
~
~
Revision: 13 T Westingh0J88 6.2 111 May 30,1997
- 6. Ergineered Safety Features F
Table 6.2.1.4 3 (Sheet i of 6)
SIASS AND ENTHALPY RELEASE DATA FOR THE CASE OF STAIN STEAh! LLST FULL DOUBLE ENDED RUPTURE FROM 102% POWER LEVEL WITH FAULTED LOOP SIAIN STEA51 LLNE ISOLATION VALVE FAILURE THAT PR DECES_liLGEEST CmmmmNT TEMPERATURE w.. w w a Sm..I ~ L.uls nowdc @
Initial stea generator mass ( lbm )
. HMW i % 7C 9 2 l
Mass added. " C _t':
- ( lbm )
-63 4 - 7 0 C l
Mass added by feedwater fit hing ( lbm )
6650- 9 5 0 i l
Innue.1 steam pressure ( p=.a,
447 W 5 2 I
Feedwater line isolauon at ( sec )
841 L 50 l
Steam line isola'!on at ( sec )
&R %56
-- s ~~
~
- '- m Time (sec)
.\\ tass Obm/sec)
Enthalpy (Btu /lbm)
Wyc) y FlV l
0.0 0.0 0.00
- c) M N I
0.1 10767.6 1198.33 M pu 0.2 10754.4 1198.36 i
0.3 10745.0 1198.38 19
~
l 0.4 10735.7 1198.40 1
0.5 10726.6 1198.43 I
0.6 10717.7 1198.45 1
077 10709.0 1198.47 1
08 10700.5 1198.49 I
0.9 10692.1 1198.50 i
I.0 10683.9 1198.52 l
1.1 1
1198.54 1
1.2 4721.4 1197.81 1
I3 4698.2 1197.93 i
1.7 4627.7 1198.29 2.1 4561.2 1198.62 I
2.5 4498.1 1
.94 I
2.9 4439.3 1199.2 I
3.3 4384.3 1199.48 I
k 3.7 4332.8 1199.72 l
}
I 4.I 4284.4 1199.95 I
h 4.5 4238.9 1200.16
(
s Revision: 13 May 30,1997 6.2 112 3 Westinghouse
TIME MASS ENTHALPY (sec)
(bm/sec) (BTU /lbm) 0.0 10886 1107 0,1 10886 1197 0.2 10871 1197 0.3 10860 1197 gned iC.9 0.4 10849 1197 0.5 10839 1197
((;h 4 \\
0.6 10829 1197 0.7 10819 1197 0.8 10809 1197 0.9 10800 1197 1.0 4962 1197 1.1 4938
-1197 1.2 4919 1198 1.3 4900 1198 1.4 4882 1198 1.5 4863 1198 1.6 4846 1198 1.7 4828 1198 4
1.8 4811 1198 1.9 4794 1198 2.0 4777 1198 2.1 4760 1198 2.2 4743 1198 2.3 4727 1199 2.4 4711 1199 2.5 4695 1199 2.6 4680 1199 2.7 4664 1199 2.8 4649 1199 2.9 4634 1199 3.0 4619 1199 3.1
-4605 1199 3.2 4591 1199 3.3 4577 1199 3.4 4563 1199 3.5 4550' 1199 3.6 4536 1199 3.7 4522 1199-3.8 4510 1200 3.9 4497 1200 4.0 4485 1200 4.1 4472 1200 4.2 4459 1200 4.3 4448 1200 4.4 4436 1200 4.5 4424 1200 4.6 4413 1200 4.7 4403 1200 4.8 4392 1200 4.9 4382 1200
i 5.0 4372 1200
-f 5.1 4361 1200
[
5.2 4351 1200 5.3 4341 1200 l
5.4 4332 1200 5.5 4322 1200 i
5.6 4312 1200 C.7 4303 1200 9
7 a$ @ ) i'
- l' 5.8 4294 1200 (O'"'"h 5.9 4285 1201.
f 6.0 4275 1201 6.1 4267 1201 6.2 4258 1201 6.3 4149 1201 i
6.1 4241 1201 6.0 4233 1201
)
d.0 4224 1201 r
6.7 4216 1201 6.8 4208 1201 i
6.9 4200 1201 i
7.0 4192 1201 1
7.1 4184 1201 7.2 4177 1201 7.3 4170 1201 7.4 4162 1201 7.5 4154 1201 7.6 4147 1201 7.7 41<0 1201 7.8 4133 1201 7.9 4126 1201 8.0 4119 1201 8.1 4112 1201 8.2 4105 1201 8.3 4099 1201 4
8.4 4092 1701 8.5 4085 1201 8.6 4078 1201
~
8.7 4072 1201 8.8 4067-1201 8.9 4061 1201 4
9.0 4055 1201 9.1 4050 1201 9.2 4044 1201 9.3 4038 1202 9.4 4023 120?
I 9.5
- 4026 1202 l
9.6 1975 1202 0.7 1972 1202 9.8 1970 1202 9.9 1967 1202 P
10 1965 1202 11 1936 1202 12 Ifp01 1203 13
- 1861 1203 4
i
.+v-w.
-w-w
,'--.n-w-~~.wm-
.m s---,
av
,%-.,.-m,y,,--,~,.,--,.,c,,s-.
m
---w-.,y
-o #,,,,,--
-.+,,--w-%i.n3--.
~,--
w-y-.
14 1818 1203 15 1712 1203 16 1726 1204 17 1680 1204 18 1632 1204 19 1579 1204 20 1525 1204 21 1482 1204 i # *
' q 3 4'N, 22 1429 1204
/
~
23 1377 1204 s
24 1327 1204 25 1279 1204 26 1234 1204 27 1190 1204 I
28 1149 1204 29 1111 1204 l
30 1074 1204 31 1040 1204 32 1009 1204 33 979 1203 34 950 1203 35 924 1203 36 899 1203 37 875 1203 38 852 1202 39 833 1202 1
40 815 1202 41 797 1202 4,
J 42 781 1202 43 764 1201 44 749 1201 45 734 1201 46 720 1201 47 707 1201 48 694 1200 49 682 1200 50 670 1200 55 621 1199 60 584 1198 65 555 1197 70 534 1197 75 517 1196 80 504 1id6 85 493 1196 90 483 1195
(
95 473 1195
{
100 44 1195 105 4L.
1194 110 445 1194 115 435 1193 120 425 1193 125 416 1193 t
130 406 1192 135 397 1192
_m.____..____
140 388 1191 145 380 1191 150 372 1191 155 365 1190 160 358 1190 165 352 1190 170 346-1189 175 341 1189 I ^ O'3 i
'4
180 336 1189 185 331 1189
(
190 327 1188 195 323 1188 200 320 1188 205 310 1188 210 313 1188 215 310 1187 220 307 1187 225 304 1187 230 301 1187 235 299 1167 240 296 1187 245 293 1186 l
250
-291 1186 255 288 1186 260 286 1186 265 283 1186 270 281 1186 275 278 1185 280 276 1185 285 273 1185 2^0 271 1185 295 268 1185 300 266 1185 306 256 1184 312 244 1183 310 230 1182 324 214 1180 330 194 1178 336 168 1176 342 135 1171 348 95 1164 354 3
1157 360 0
1158 6
i 4
e
- 6. FogimrW Safny Teamm j
l Table 6.2.1.4 3 (Sheet 2 of 61 StASS AND ENTHALPY RELEASE DATA FOR Ti(E CASE OF htALN STEAh! LLNE FULL DOUBLE ENDED RUPTURE FRCh11029, POWER LEVEL WITil FAULTED LOOP hlALN STEAh! LINE ISOLATION VALVE FAILURE TilAT PRODUCES lilGi(EST CONTALNhfENT TEh!PERATURE
~WUs (IbiR!m)
EnthBtdhnt
/{ litne'(mI ~~~ ' '
I 49 4197.8 1 0034 1
53 41015 1200 51 i
57 4125.2 1:00.66 I
i 61 4091.8 1200.80 1
65 4060.3 1 00.94 j
l 69 4030.5 1:01.0(
I
?3 4002.3 1201.13 1
77 3975.6 1:01 29 1
8.1 3950.2 1201 39 I
8' 3925.7 1:01.49 1
89 3903.9 1:01.58 l
9.3 3883.2 1:01 66 I
97 3861.9 1:01.74 1
10 1 1901.4 1201.97 l
10 5 1890.9 1202.05 l
10 9 1879.5 1202.13 11.3 1867.2 1202.22 11.7 1854.0 1202.31 i
i 12,1 1339.9 1202.41 12.5 1825.0 1202.5I I2.9 1809.3 1202.62 j
13.3 1793.0 1202.72 f
13.7 1776.2 1202.83 4
1 14.1 1758.9' 1202.94 1
14.5 1741.4 1:03.04 I
9 1723 6 1203.15 Revision: 13
[ Westingh0044 6.2 113 Stay 30,1997
- 6. E:gineered S:fety Features I
Table 6 2.14 3 (Sheet 3 of 6)
$1,.3S AND ENTilALPY RELEASE DATA FOR THE CASE OF.'.!ALN STEASt LINE FULL DOUBLE ENDED RUPTURE FROST 102"e POWER LEVEL WITH FAULTED LOOP SIAIN STEASI LIN'? ISOLATION VALVE FAILURE THAT PRODUCES HIGl(EST CONTAIN5!ENT TE31PERATURE
' Time (sec)
Stass (Ibm /sec)
Enthalpy (Bru/lbm) l 15.3 1705.7 1203.25 l
(
15,7 1687.8 1203.35 l
16.1 1670 0 1203.44
/
I 16.5 1632.3 1203.53 1
16 9 1634.8 1203.62 l
17.3 1616 8 1203.70 l
17.7 1598.0 1203.79 l
l 8.1 1578.6 1203.87 l
18.5 1558.7 1203.95 l
18 9 1538.3 1204.03 1
19 3 1517.6 1204.10 l
19 7 1496.7 1204.17 1
20.5 1465 3 1204.25 1
22 5 1363 6 1204 42 1
24 5 1266 8 1204 48 I
26 5 1179 2 1204.4I I
28 5 1100 0 1204.25 i
30 $
1029.8 1204.01 1
32.5 968.1 1203.70 1
34.5 913 4 1203.35 1
36.5 864 5 1202.96 1
36.t 820.7 1202.54 I
i 40 5 781.3 1202.11 1
42.5 745.3 1201.66 I
i 44.5 712.9 1201.19 l
46.5 683 6 1200.7%
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Revision: 13
$1ay 30,1997 6.2 114
[ W8Stingh00$4
- 6. Engineered Safety Features l
Table 6.2.1.4 3 (Sheet 4 of 6)
MASS AND ENTHALPY RELEASE DATA FOR THE CASE OF MAIN STEAM LLNE FULL DOUBLE ENDED RUPTURE FROM 102% POWER LEVEL %TTH FAULTED LOOP MAIN STEAM LLNE ISOLATION VALVE FAILURE TIIAT PRODUCES HIGHEST CONTAINMENT TEMPERATURE (Time (sec)
Mass (Iben/sec)
Enthalpy 1Bru/lbmh I
(-
48.5 659.1 1200.30
)
50.5 639.7 1199.93 l
52.5 621.7 1199.57 I
54.5 605.3 1199.22 1
56.5 590.6 1198.89 I
58.5 577.3 1198.59 I
60.5 565.4 1198.30 l
62.5 554.8 1198.03 l
64.5 545.2 1197.79 I
66.5 536.7 1197.56 f
I 68.5 529.I i197.36 1
70.5 522.2 1197.17 I
72.5 516.0 1196.99 I
74.5 510.4 1196.83 1
76.5 505.3 1196 69 I
78.5 500.6 1196.55 I
80.5 496.3 1196.42 1
82.5 492.2 1196.29 I
84.5 488.3 1196.17 86.5 4 84.5 l196.06 i
88.5 480.8 1195.94 I
90.5 477.2 1195.82 I
92.5 473.6 1195.7!
l 94.5 470.1-t 195.59 I
96.5 466.5 1195.47 I
98.5 462.9 1195.34 Revision: 13 y Westinghouse 62115 May 30,1997
- 6. Engineered Safety Fectures l
l Table 6 2.14 3 (Sheet 5 of 6) 51 ASS AND ENTIIALPY RELEASE DATA i
FOR THE CASE OF StALN STEA31 LLNE FULL DOUBLF.
ENDED RUPTURE FROh! 102, POWER LEVEL WITH FAULTED LOOP STAIN STEAh! LINE ISOLATION VALVE F AC.URE TilAT PRODUCES lilGIIEST CONTAINSIENT TEhfPERATURE
!( Time (sec)
.%lan fibm/sec)
Enthalpy (Brullbm) i 101.0 458.8 1195 20 I
105.0 451.6 1194.94 I
I i
109 0 444.0 1194.66 1
l 113 0 436.3 194.36 I
117.0 428.4 1194.06 -
l 121.0 420.6 1193.74 I
I25.0 412.9 1193.42 I
I29.0 405.3 1193.09 I
I33.0 397.9 1192.76 l
137 0 390.9 '
l192.43 1
141.0 354.1 1192.12 I
I45.0 377.6 1191.82 1
149 0 371.5 1191.53 l
153.0 365,6 1191.24 I
I57 0 360.2 1190 77 l
161.0 355.0 1190.72 I
I65.0 350.2 1190 47 l
169.0 345.6 1190 23 I
I73.0 14i.5 i190 0l I
177.0 337.5 1189.80 l
181.0 333.7 II69 60 185.0 330 2 1189 41 I89.0 326.9 1I89.23 193 0 323.8-1189.05 l
197 0 320.8
!!88.89 i
I
\\
202.0 317.7 1188.71 L
~
Revision: 13 Stay 30,1997 6.2 116 3 Mstinghoust
.a.
- 6. Engineered Safety Features 1
Table 6.2.14 3 (Sheet 6 of 6)
StASS AND ENTHALPY RELEASE DATA FOR TIIE CASE OF STAIN STEAS! LLNE FULL DOUBLE ENDED RUPTURE FROST 102"e POWER LEVEL WirH FAULTFD LOOP %1AIN STEASI LINE ISOLATION VALVE FAILURE TilAT PRODUCES IIIGIIEST CONTAINh!ENT TEhiPERATURE Time (sec)
Stass (Ibm /sec)
Enthalpy (Btuabm)
I 2l00 312.6
!!88.42 j
l 218.0 307.8 1188.15 I
l
- 60 303.3 1187.88 j
l 234.0 299.0 1187.62 1
242.0 294.7 1187.37 1
250 0 290.5 1187,12 l
258 0 286.3 1186.36 1
266 0 282.2 1186 $9 I
274 0 278.0 1I86.32 1
282.0 273.8 11 $6.03 l
290 0 269.6 1185.74 i
298 0 265.4 1185.45 l
306 0 255.6 1184.73 1
314 0 238.8 1183.41 1
3:20 218.0 1181.60 8
330 0 189.5 1178.83 I
l 338 0 149.0 1174.23 I
1 346 0 96.7 1165.42 l
l 354 0 0t 1158.98 I
362.0 0.0 1159 02 1
370.0 0.0 1159 02 R'evision: 13
[ Westiflgh0034 6.2 117 Stay 30,1997
- 6. Engineered Safety Features Oa 4
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@ Westingh00sg 6.2 143 May 30,1997
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@ Westinghouse 6.2 145 May 30,1997
- 6. Ecgineered Safety Features t
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- 6. Engineered Safety Features 0
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- 6. E:gineered Safety Fes::res
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@ WtWinghoust 6.2 151 May 30,1997
- 6. Engineered Safety Features O'&
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May 30,1997 6.2 152 3 Westingh0056
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Figua 6.2.1.1 11 External Pressure Analysis Containment Pressure vs. Time ReWI,n: 13
@ WBStingh00se 6.2 153 May 30,1997 I
- n
- 6. Engineered Safety Features
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6.2 154 Westinghouse
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20000 40000 50000 80000 100000 IIme (S8C) e K
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[-
Revisioc 13 OT Westinghouse 6.2-155 May 30,1997
4 I
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4 ATTACHMENT 3 DESCRIPTION OF CHANGES TO THE AP600 CGi4TAINMENT EVALUAllON MODEL (1) Upgrade of WGOTHIC version 4.1 to version 4.2 The SSAR DBA pressure transients (DECLG LOCA and MSLB) have been recalculated using WGOTHIC version 4.2. Identified errors in the WGOTHIC clime subroutines, the' were previous y evaluated to have no significant impact on pressure results, have been corrected.
The changes that were made to WGOTHIC version 4.1 to create version 4.2 are as follows.
created a new clime subroutine, gvel, to provide cell-centered velocity direction for the clime calculations, to allow correct determination of assisting versus opposed convection in the downcomer; replaced the modified GOTHIC ccvel subroutine, supplied by NAI, with the GOTHIC 4.0 ccvel subroutine and corrected the error in effective flow area calculation; replaced the single p,ecision constants with double precision constants in subroutinea mixed.f and props 1.f; increased the array dimensions for the GOTHIC conductors.
Thus, known errors in the WGOTHIC clime subroutiner have been corrected. In addition, known errors reported for GOTHIC version 4.0, the basis for WGOTHIC versions 4.0 and beyond, have been evaluated and determined not to be applicable to sections of coding exercised by the evaluation model.
Verification and validation of the code changes has been completed. As part of the validation effort, a regression test was performed to confirm that the change from WGOTHIC version 4.1 to version 4.2 had no effect on calculated peak pressure.
(2) Changes in the Evaluation Modelinput Calculations, which provide the geoinetric data (free volume, hydraulic diameter, pool area, flow path parameters) for input to the WGOTHIC containment pressure DBA, have been updated to be consistent with the latest drawings. Applicable rr:odfications have been made to the AP600 containmant evaluation model input to reflect the changes in geometry, as follows.
Flow areas between the steam generator compartments and the CMT rooms have been increased from [
)".
CMT volumes were updated.
1
...~ ~
[c.
- : Curb height cnd r: lated flow path cnd heights for tha ceiling openings in the cccumulltor -
. and CVS compartments were modified.
4 IRWST free volume was changed.
1 Mass and energy _ release for containment pressure DBA DECLG LOCA was updated to account for revised IRWST volume.
Additional input changes made to the AP600 containment evaluation model for SSAR
[
containment pressure DBA calculations, relative to the evalut.: ion model described in WCAP.
14407, Rev.1 are as fol;ows:
The gap between steel and concrete in the modeled steel jacketed concrete has been increased from 5 mils to 20 mils to reflect the results of an evaluation by Westinghouse regarding the AP600 containment steel / concrete interface.
To increase solution accuracy, the numerical mesh resolution was ;ncreased for the concrete internal heat sinks and the concrete portion of the steel-Jacketed-concrete internal j
heat sinks. From an internal neat sink mesh refinement sensitivity,-it is concluded that the selected concrete mesh conservatively underpredicts heat removal by the internal heat sinks.
The area for flew path 268 was corrected from [
f# square feet to [
T* square feet, l
and form loss coefficients were [
f# for paths 259,260,262. These paths connect lumped parameter volumes between wh:,:h there are insignificant flow path restrictions ano e
which were previously provided finite loss coetficients, b
Of the 212 conductors modeled, minor corrections were made to three regarding heat transfer coefficient type, thickness, surface area, or location. In add;ilon, eight conductors were reallocated between CMT North and CMT South volumes, based on compartment volume changes; - and five conductors, which were neglected in the previous model, have been added: [
f*.
The mass and energy releases for the MSLB were revised to account for potential thermal expansion of the flow restrictor area, as well as more accurate initial steam generator mass, feedwater flashing volume, steam line header volume, and revised startup feedwater model.
The PCS evaporated flow versos time input was calculated using the metodology describ6d in WCAP-14407 Rev.1, Section 7.
- c t
An evaluation' has been performed to show that the changes to intomal containment -
parameteydo not' affect the case-to-case sensitivities used to select the limiting extremes for intemal initial and boundary conditions. Since the intomal heat sinks reach their maximum
. therma! effectiveness well before the DECLG LOCA peak pressure is reached, the changes i
2-F y
+,w-
,w
,.v-.-m
s' i_,-
do not significantly impact the sensitivities used to select limiting scenarios f:r circulation cnd stratification. The small change to internal pressure, and thus the related small change to
' internal temperature boundary condition for the ' containment shell, does not affect the
' sensitivities for clime vertical noding and conductor mesh. Similany, the changes do not affect external condition case to-case results. The changes also do not invalidate the time step study. Therefore, the sensitivities performed in WCAP 14407, Rev.1,~ remain valid.
3 E
_