ML090400654

Response to Requests for Additional Information Regarding Amendment Application Numbers 252 and 238 Replacement Steam Generators

ML090400654
Person / Time
Site:	San Onofre
Issue date:	02/05/2009
From:	Scherer A Southern California Edison Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML090400654 (40)

Text

SOuTHERN CALIFORNIA Withhold from Public Disclosure Under 10 CFR 2.390 A.Edward Scherer a EDirector N When Separated from the Proprietary Enclosure Nuclear Regulatory Affairs An EDISON INTERNATIONAL Company (Enclosure 2) This document is Decontrolled February 5, 2009 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

Docket Nos. 50-361 and 50-362 Response to Requests for Additional Information Regarding Amendment Application Numbers 252 and 238 Replacement Steam Generators San Onofre Nuclear Generating Station, Units 2 and 3

References:

1. Letter from J. T. Reilly (SCE) to Document Control Desk (NRC), dated June 27, 2008;

Subject:

Docket Nos. 50-361 and 50-362, Amendment Application Numbers 252 and 238, Replacement Steam Generators, San Onofre Nuclear Generating Station, Units 2 and 3

2. Letter from A. E. Scherer (SC) to Document Control Desk (NRC) dated August 13, 2008;

Subject:

Docket Nos. 50-361 and 50-362, Additional Information regarding Amendment Application Numbers 252 and 238, Proposed Change Number NPF-10/15-583, Replacement Steam Generators, San Onofre Nuclear Generating Station, Units 2 and 3

3. Letter from N. Kalyanam (NRC) to R. T. Ridenoure (SCE) dated November 4, 2008;

Subject:

San Onofre Nuclear Generating Station, Units 2 and 3 - Request for Additional Information Regarding the License Amendment Request to Support Replacement Steam Generators (TAC Nos. MD9160 and MD9161)

4. Letter from N. Kalyanam (NRC) to R. T. Ridenoure (SCE) dated December 8, 2008;

Subject:

San Onofre Nuclear Generating Station, Units 2 and 3 - Request for Additional Information Regarding the License Amendment Request to Support Replacement Steam Generators (TAC Nos. MD9160 and MD9161)

Dear Sir or Madam:

Reference 1 provided a License Amendment Request for the San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 regarding replacement of steam generators. The proposed changes related to Steam Generator Tube Inspection and Repair Criteria and a revision of AO 1 P.O. Box 128 San Clemente, CA 92672

Document Control Desk February 5, 2009 the peak containment post-accident pressure and temperature. Reference 2 provided additional information related to NRC review of Reference 1.

By References 3 and 4 the U. S. NRC requested additional information from Southern California Edison (SCE) to support the review of Reference 1. This letter provides a response to the NRC questions contained in References 3 and 4. to this letter provides a Westinghouse authorization letter CAW-09-2527 with accompanying affidavit, Proprietary Information Notice, and Copyright notice.

The Westinghouse affidavit in Enclosure 1 sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed by paragraph (b)(4) of 10 CFR 2.390. Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR 2.390. provides a proprietary version of the response to the NRC's requests for additional information. provides a non-proprietary version of the response to the NRC's requests for additional information.

In addition, as part of the development of the response to these requests for additional information, SCE has determined that two items in Reference 1 require clarification.

In the Enclosure to Reference 1, Table 4.2-4 provided values for maximum post-accident peak pressures and temperatures for the analyzed cases. The times to peak containment pressure and vapor temperature for the bounding Equipment Qualification case as reported in Table 4.2-4 should be revised to 168 seconds and 36 seconds, respectively, to be consistent with the Table 4.2-4 results reported for the Main Steam Line Break (MSLB) case of zero percent power with a Main Steam Isolation Valve (MSIV) single failure. Although the peak containment pressure and temperature occur as described above, the peak containment pressure is essentially constant from 160 to 180 seconds and the peak vapor temperature is essentially constant from 35 to 36 seconds following event initiation. Although the reported times are revised, there is no effect on the conclusions of Reference 1.

Secondly, Table 4.2-1 of the Enclosure to Reference 1 summarizes the significant inputs for the Loss of Coolant Accident (LOCA) Containment Response Calculations. The first row of this Table, "Sources of Energy," describes the amount of main feedwater inventory modeled and refers to the feedwater pump trip as the point in time at which modeling of the feedwater inventory changes. This description should have referred to closure of the Main Feedwater Isolation Valves as the appropriate timing point. Although this description of the timing for consideration of feedwater inventory was different than used in the model the amount of energy modeled was accurate in the analysis, is consistent between the original steam

Document Control Desk February 5, 2009 generators and the replacement steam generators, and there is no effect on the conclusions of Reference 1.

There are no new regulatory commitments contained in this letter.

Should you have any questions, or require additional information, please contact Ms. Linda Conklin at (949) 368-9443.

Sincerely,

Enclosure:

cc: E. E. Collins, Regional Administrator, NRC Region IV N. Kalyanam, NRC Project Manager, SONGS Units 2 and 3 G. G. Warnick, NRC Senior Resident Inspector, SONGS Units 2 and 3 S. Y. Hsu, California Department of Public Health, Radiologic Health Branch

Enclosure 1 Westinghouse Authorization Letter And Affidavit

SWestinghouse 'Rsin~u-REecti Nuctear kr,,ces V-,OBoxx 3t55 cCnpy Pittsburgh, Penns'jtva nia l $?3O-3*

UStA U.S. Nujclear Regulatory Cmmnission Oirect tal: (412) 374-4643 Documeiu Control Desk Direcifaxs (412) 374-4011 Washington, DC 20555-0001 einaI; .

Our rrf: CAW-09-252?

elebwary 3, 2009 AI'PLICATION FOR WITIH[IO[.DING PRO P -FT.A.Y INFORMATION FRQI PUBLIC DISCLOSURE

Subject:

Southern Califor-riae 1di.s)n Company's Response to RAIs Contained in NRC Let!ers l)atedt November 4,2008 and December 8, 2008, N. Katyanam (NRC) to R. Ridcnourc (SCE), TAC Nos. MD 9160 and MD 9161, (Pmprictary)

The prpritary information in die subject RAI responses lbr which withholding is,being requested is further idemtified in Aflidavit CAW-09-2527 signed by 01c owner of th proprietary inCoraiovn, We-stinghousc ELectric Company LLC. The affidavit, which accomppniei this lcttr, sets forth the basis on which Elie iRtIrmnatiorn ruy be witlhheld from public disclosure by the Commntision and addresses with specticity the considcrations listed in paragraph (b)(-.) of I0 CFR .ection 201 ofile Commtlission's regu!aionrs.

Accordingly. ;his letter auchorih,. urse L fhC thC0WompanWiyng affidavit by Southern Califumia Edison Company.

Conresporidendc with repect to the pmprietary aspects of the application for withh,:lring or the Westinghouse affidavit should rek-erencr this [etter, CAW-09-2527, and should be addressed to I A. Gresham, Manager, Regrlsitory Compliance and Plant Licensing, Westinghouse Elcctric Comoany LLC, P.O. Box 355, Pittsburgh, Pennslvmania 15230-0355, Vey truly yours,

1. A.Gresham, jaRager Regttlatotw Compliance and Plant Licensing Enei*sures

CAW-U9-25217 ALFFIDAVFt-STATF OF C 04NR.Cf[CkjT:

COUjNTXY OF HARTFORD:

Bdcorc tne. the undersieicd audliority, pcisonaIty appearcd M. J. Ga-carz, who. being by mc duiy sworn accomrduu lo dcposes and says ttat he is authorized to execule this Affidavit on behalf of Wu~snimghiuusr Elemtric Compa.y LLC. (Westiniirouse), and hai. the aver-Nents of facl ses foioth in this Affidanvii arc. tirw and correc t th¢ best of his kOwl-ed~c, infonrmatim, and be]id':

<--

Sysitms and pquipmeni -E"rqjiiietrirngH Swom to anid subscribed bcfore nie this!-3~ day o** 2009 N'o i 'ovPublic My Commission Extpires; _________

2 l am Manager, Systems and Equipment EngineerineP It, in Nuclcar Services. Wcsinghousc I)

Electric Company LLC (Westinghouse)? and as such, I have been specificaily delegated the function ofreviewing the proprietary inforination sought to be withheld from public disclosure in cotuiection with nuclear power plan! licensing and rule making proceedings, and am muthorized to apply 1kr its withholding on behalf of Wcstinghouse.

I am making this Affidavit in confonnmice with the provisions of 1t0 CFR Section 2.390 of the 12)

Commission's regulations and in conjunction with the Wesvirthouse "Application for Withholding" accompanying this Affidavit-(3) 1 have personal knowledge of the criterig and procedures utilized by' WestinghouWs in designaling information as a trade secrcl, privileged or as confi-dential comircrczial or financial i'dormnation, (4) Pursuant to (he provisions of paragraph (b)(4) of Section 2.390 of the Conrmni ssion's regulalions, the Following is ftirnishecd for consideration by the Commission ht dctcrmining whether t11C information sor.hýt io be withheld from p.blic disclosure should be withherd.

(G) [he ifit'mnatiotn sought to be wihheld Cron public disclosure is owned 2nd has been hed inl con lidenue by WestintI.Ltuse.

(ii) The informrraion is of a type customarily held in contfidcence by Wcsinghouse and not customarily disclosed to tbe public. Westinghouse has a rational basis for determinin;ig the ;tYp of i.ltibnntalion c~ustomairilv held in, corfidence by it and, in that coartection, utilizes a system to determine when and whether to hold cerain types of infonuat*on in confidence. The applicationrOf that system and the substance ofihat systcm constitutcs Westinglhousc policy and provides the ratiotonlt basis required.

Under that system, infonnation is.held in conFidence if it falls in one or more of several types, she release of which might result in the loss of an existing or potential competitive advantage, as follows:

(a) The informationt reveahl the distinguishing aspects of a process (or componet.,

structurc, tool, method, e1c.) whete prevention of its use by any of

iicstsnghouu*es compelicmrs without license ffiom We;ti*-*hot"c con'nsiLutelit i*

competitive ecomomie advantage over other compamcic-.

(b) Ii cotsisis ofsuppon*inL dam, i dloudit.g lest daita, relalive.to a process (or co, ponent, structure, too!, method, etc.), the application of which data Secures at

,ompetitiveeconoomni advantage, e.g-, by optimization or improved marlketability.

(c) Its use by a conipetitor would reduce his expeniditoire of resours Or improve his conipetitie position in the design, tmranuflacture, shipment, installation, assurance of quality, or licensinq similar product..

(d) It re','eal5 cost or price infomnation, prodjctdon capacities, budget ]evels, or commercial strategies ofWcstinghlWrusC it's CUSit10oeis or sLIpp!h J-

{e} It reveals aspeeou of past, preCent, Or FUtI2re WCS ingh*uS- or CLstAImrer furded dtevelopnent plans and progmrams ofpoltei'alt eommercial value to Wcestingliou se, (0i it contains patentable ideas. for which patent protec.iorn -maybe desirable.

There are sound policy resons behind the Westinghouse sys1em which inc:ldw the lotlitwing:

(a) 'I e use of such iufum7stfo iis by Westinghousc gives-i "Wscinghosuse a compctitive advantage over its compet.itors. ft is, therebore, wiihhed from diselosure to protect the W\V'joPlhoius competitive position, (b) It is infbrmat ion that is marketable in many &ays. The exte It to which such int',nmamion is available Wtcompelitors diminrtishes the Westinghouse ability to sell p1roducts and services invalving Ithe tise of the inforvalion, (Co Uwsby our ;ompetitor wouald put Westingliousc at a eotnpeti, ivr disadvantage bY reducing his expenditure of resources at Our eXpense,

4 CAW-U9-2527 (d) Each-cot p.tieat of proprietary innntiottto pertinent to a particular competitive advuntane is potentiallIy as valuable as the total competitive advantage. If competitors ticquire cormpoents of proprietary in formatinn, any one component may be the key to the entire pu..-le, thereby depriving Westinghouse of a competilive advantage, (e) Unrestricted disclosure wouldjeopardize the position of prominence of Westinghouse in the world market, and lhereby give a9market advantage to the cormpetilion ýt those countries.

(0 The Wcstinghousc capacity to invest corporate assets tin reseamth and development depends upoit the success in obtairtine and maintaining a

.ormpetitive advantUgei (iii) The infomrrnsion is being transmkied to flie Commission in confidence Ltid, nider thie previsions of IQClR Section 2.390, it is to be received in eonfidertcc by !he Conmislon.

(iv) The itotmrati*.t sought t, be protectd is not availablc in public sources or available information has not been prCviously enploy-d in the same original manner or method to the best ofosr krnowledgc and belief.

(v) The proprietary inifornatiot sought to be withheld in this submittal is that which is appropriately marked in Souohen California Edison Company's rcsponse to Rcquests lbr Additional Inforniation (RA*,) conitained itt NRC's letters from N. Kalyanam (NRCj tu R.

Ridenutre (SCE) dated November 4, 2008 and December 8,2008, TAC Nos. MD9160 and MD 91 61, the response being transmitted by Southet* California Edison Cotnpany's letter and Application for Wiftitolding Proprietary itnformsation froti Public Disclosure to lhe Document Contiol Desk. The proprietary ikLf~nnatiorn as s;ubmitted. by Westinghouse for use by San Onofre Nuclear Generatin4 Station Units 2 and 3 is expucted to be applicable for other licersee submittals in response to certain NRC retluirements for justification of mrss and unergy release: calculations asswciated with replacement steam generators.

5 CAW'°O9-252?

This inllormation is part ofthat which Westinghouse used to permbin mass and energy release Calculatiomrs assuciated with r.pliaeement stear generators n-d which WNtinghouse has compiled to justify the appropriatcn,.,s of those calcuhuliona. Further, the informadon has subsiantial com*nrcrial valun rclatcd to Westinghouse's ability to sutpporl replacement sleam gcncratvr analyi~cal services and as inpui for ainalyses requiring the information sought to be withheld.

Public dLsclosure of this proprietay information is likely to cause substaiaial hairn to t[le competitliv posilimn of Westinghomue because it would enhanct: the ability of competitors to providc similar calculati5on ar lidensing defense scrvicUs For cOMMereial power reactors with'out eonuncnstaratc expenses,, Also, public disclosure. oftheb informantion would enable others to use the irfbnnation to meet NRC requiremi*ts for licetnsing Jocmentat ion without putliasimi the right to use the inforrtation.

The development of the tachnology described in pnrt by the intiftortion is the result of applvintg wh,esults of many:years of experic-nce inan in.ensive West.inehouse effort and the cxpenditure ofacoossiderable sumn of tioney..

In order for compiitvos of We nghusýe to duplicate [his infonmltion, similar t chnieiJ programs woultd have to bc perfobried arnd a significant manpow*r effort. having the requis*.i talen and experiencc, would have to In expended.

Further the dupormit sayethrnot.

CAW-09-2527 PROPRIETARY INFORMlATION NOTfICE Transmittd herewith are proprietary andior non-propriciary versions of duoenuctts furnished woilc NRC in conmection with recquests for generic and/or plant-gpeefic review and appruval.

In order to corfon.n to the requirements of I0 CFR 2.!RG of the Commissinn', reguaionf norlcering the protection nFproprictary inforem ation . stubrmitted to the NRC, the iniforiation which is proprietary ii, the proprietary versions is contained within braekets, and Where the proprietary infUnration has been deleted in the non-pruprietary versions, only the brackets remain (lhe. informiation that was contained within the brackets in the proprietary versioms having been deleted). The justiticationt for claiming the information so designaled as proprietary is indicated in both versions by means of lower case letters (a) through (1) located as a sk.ýpcrscript immnediately following the brackets enclosing each item of inninmation being identified as proprietary or in the margin Opposite such information. These lower case I.Ittes refer Io the Ipcs of information Westinghouse. eustomarily holds inco-fidene identified ii. Sections (4)(ii}(a) through (4)(ii)(fl) ofthie affidavit accompanying this transmittal pursuant to 10 CFR 2.190(b)(1).

CAW-09-25 27 COPY-RIGHIT NOTICR The d cumenrts IrmaIISmIitted hcrewith eachi bear a copyright nntice. The NRC is permitted to make ihe number of copi*es of the inforniation contained in these docuuments which ate necessary -or siuitenial use in connection with, genueric and piawt-spec.ific reviews and ,pprovnls as w,]-a5 the issuance, denial, ameniment, transfer, renewal, modifincation, suspension, revocation, or 'iioLation of a license, permit.,

order, or regulation subject to the requirements of 10 CFR 2-.90 regarding restrictions on public disclosure to the cxteni such information has been idtmified as propriclarv, copyright protection not0withstanding. With respect to the non-pmoprietary ve.sionrs of Ihes, dCocumtnis, the NRC is ipcmniettcd to make the numbecr ofcopies beyond those necessamy for its intermsl use which are necessary in order to have one copy avaiLable for public viewing in the appropriate docket files in the public documrCn room in Washington, DC and in local public docunment rooms as may be required by NRC rcgrulations ifDhe number of copies .ubmirred is insufficient for this pur)Ose. Copic* made by the NRC must include tht copyright notice in a-! instances and the proprictary notice if the original was identifiecd as propfietary.

Westinghouse Non-Proprietary Class 3 Enclosure 3 Response to RAIs, Non-Proprietary

Westinghouse Non-Proprietary Class 3 Page I of 27 Response to Request for Additional Information Dated November 4, 2008 r

Response to RAI 1 RAIl: It was stated in Section 3.0 of the enclosure to the LAR that the containment post-accident pressure, mass and energy analyses for the design basis Loss-of-Coolant Accident (LOCA) and Main Steam Line Break (MSLB) used the existing methodology while accounting for the differences between the RSGs and the existing SGs. Section 4.2.1.2 mentions examples of the differences such as greater water volume, higher secondary side operating pressure, greater heat transfer area and larger metal mass. Please quantify the differences between the RSG and the existing SG to the extent they were used in the analyses.

Response 1: Table 1 provides the mass-energy and containment pressure-temperature response analyses input parameter changes due to differences between the Replacement Steam Generators (RSG) and the existing steam generators (also referred to as Original Steam Generators, OSG). The values provided in Table I are compared at full power operating conditions. The response to RAI 2 provides the input parameter changes that are not due to steam generator design differences.

Table 1: Analysis Input Parameter Changes due to RSG Design Changes ITEM I PARAMETER OSG VALUE RSG VALUE COMMENTS*

I Pounds of water left Limiting Case hot leg Limiting Case hot leg Primarily due to the in the primary system break value was break value is RSG design change available to be 172061 lb 176134 lb with minor evaporated by decay contribution from heat or metal-water other parameters reaction heat, as (such as fuel).

modeled in LOCA containment Pressure-Temperature (P-T) response analyses.

2 Time at which Limiting Case hot leg Limiting Case hot leg Time corresponds to COPATTA begins break value was break value is 12.5 end of blowdown.

performing mass and 12.2 sec sec End of RSG energy balance blowdown is later due calculations for water to increased RSG within the reactor volume.

vessel, as modeled in LOCA containment P-T response analyses.

©2009 Westinghouse Electric Company LLC and/or Southern California Edison All Rights Reserved

Page 2 of 27 ITEM I PARAMETER OSG VALUE RSG VALUE COMMENTS 3 Sensible heat and Various values Various values Primarily due to the steam generator (e.g., See Table Ic) (e.g., See Table Ic) RSG design change energy inputs, as with minor modeled in LOCA contribution from containment P-T other parameters response analyses (such as containment passive heat sinks).

Mass - Energy and Various values Various values The mass - energy Spillage Data, as (e.g., See Tables I d (e.g., See Tables I d release and spillage modeled in LOCA and Table le) and Table le) data differ due to and MSLB RSG design changes containment P-T discussed in Items 5 response analyses through 3 1.

5 Hot Plenum & Piping 3055.12 2998.27 RSG design change Volume, ft3, as modeled in MSLB Mass-Energy (M-E) release analyses Steam Generator 2523.83 2898.84 RSG design change Tube Active Volume, ft3, as modeled in MSLB M-E release analyses 7 Cold Plenum & 3974.51 3701.74 RSG design change Piping Volune, ft3 , as modeled in MSLB M-E release analyses 8 Hot Pipe Coolant 27247.37 26714.78 RSG design change Equilibrium Mass Specific Heat, Btu/IF, as modeled in MSLB M-E release analyses 9 Cold Pipe Coolant 60073.26 68235.92 RSG design change Equilibrium Mass Specific Heat, Btu/°F, as modeled in MSLB M-E release analyses 10 Initial Secondary 900 850 The values differ due Pressure, including to changes in the water in feedwater RSG operating point pipe (psia), as parameters.

modeled in MSLB M-E release analyses II Steam Generator 22803.3 23100.0 RSG design change Volume, ft3 (Total),

as modeled in MSLB M-E release analyses 02009 Westinghouse Electric Company LLC and/or Southern California Edison All Rights Reserved

Page 3 of 27 ITEM I PARAMETER OSG VALUE RSG VALUE COMMENTS 12 Initial Secondary 322901.4 320540.6 RSG design change Liquid Water Mass, Ibm (Total), as modeled in MSLB M-E release analyses 13 Initial Secondary 29012.46 30229.93 RSG design change Steam Mass, Ibm (Total), as modeled in MSLB M-E release analyses 14 Secondary Volume 3349.57 3825.204 RSG design change Required in One Steam Generator to just cover SG tubes, (ft 3), as modeled in MSLB M-E release analyses I5 Overall Heat Transfer 5.875 E8 6.214 E8 RSG design change Coefficient, Primary Coolant to Tubes, Btu/hr-°F, as modeled in MSLB M-E release analyses 16 Overall Heat Transfer 4.873 E8 5.695 E8 RSG design change Coefficient, Tube to Secondary Two Phase, BtuL/hr-°F, as modeled in MSLB M-E release analyses 17 Steam Generator 50182.2 48512.94 RSG design change Tube Mass Specific Heat, Btu/°F, as modeled in MSLB M-E release analyses 18 Steam Generator See Table la See Table I a RSG design change volumes vs. flow areas vs. heights, as modeled in MSLB M-E release analyses.

19 Feedwater enthalpy, 427.368 420.09 The values differ due including water in to changes in the feedwater pipe, RSG operating point Btu/lbm, as modeled parameters.

in MSLB M-E release analyses

©2009 Westinghouse Electric Company LLC and/or Southern California Edison All Rights Reserved

Page 4 of 27 ITEM PARAMETER OSG VALUE RSG VALUE COMMENTS 20 Break type, as Slot Break Guillotine Break with As discussed in modeled in MSLB isentropic and Moody Section 4.2.4 of the M-E release analyses (fL/D=5) correlation PCN-583 License Amendment Request, Break flow area, ft2 , 8.85 7.406 due to the steam flow as modeled in MSLB restrictor devices M-E release analyses installed in the RSG outlet nozzles, the limiting RSG main steam line break sizes are modeled 2 as 7.406 ft double-ended guillotine breaks.

21 Area at break seen by 7.87 7.406 The OSG models the intact unit, ft2, as 38 inch diameter modeled in MSLB OSG exit steam M-E release analyses nozzle flow area, which is greater than Area of steam line 7.87 7.406 the main steam line from intact unit to flow area.

header, ft2 , as modeled in MSLB The RSG models the M-E release analyses main steam line flow area, which is greater than the RSG exit nozzle flow area with its steam flow resttictor device.

22 Thin metal energy See Table lb See Table lb The values differ due storage values, to RSG versus OSG Btu/0 F, and tube support, wrapper two-phase volume and separator design which immerses thin differences.

metal energy storage values, ft3 , as modeled in MSLB M-E release analyses 23 Area of the flow 7.87 2.8 The RSG outlet restrictor, ft3 , as nozzle design features modeled in MSLB an internal flow M-E release analyses restrictor, which is not present in the OSG design.

24 Number oftubes/SG, 9,350 9,727 RSG design change as modeled in LOCA M-E release analyses 25 Number of plugged 425 0 RSG design change tubes/SG, as modeled in LOCA M-E release analyses

©02009 Westinghouse Electric Company LLC and/or Southern California Edison All Rights Reserved

Page 5 of 27 ITEM PARAMETER OSG VALUE RSG VALUE COMMENTS 26 Tube ID, in, as 0.654 0.664 RSG design change modeled in LOCA M-E release analyses.

27 Tube average heated 726.64 729.56 RSG design change length, in., as modeled in LOCA M-E release analyses 28 Heat transfer area, ft2, 106,114 116,000 RSG design change as modeled in LOCA M-E release analyses 29 Primary side fluid 1870.33 2001.0 RSG design change volume, ft 3, as modeled in LOCA M-E release analyses 30 Secondary side fluid 9,985 10,118 RSG design change (water and steam) volume, ft3, as modeled in LOCA M-E release analyses 31 Total SG metal mass, 1,242,369 1,334,393 RSG design change Ibm, as modeled in LOCA M-E release analyses

©2009 Westinghouse Electric Company LLC and/or Southern California Edison All Rights Reserved

Page 6 of 27 Table la Table la OSG Volume vs. Area vs. Height RSG Volume vs. Area vs. Height Volume Height Area Volume Height Area (cu ft) (in) (sq ft) (Cu ft) (in) (sq ft) 1 0 0 88.027 1 0 0 90.0 2 1993.729 270 88.027 2 2223.906 295.8 90.0 3 3349.566 357.624 295.979 3 2341.512 308.4 90.0 4 3349.571 357.624 295.979 4 2429.64 317.4 132.8 5 3349.576 357.624 354.122 5 3516.144 371.4 315.5 6 8116.73 519.624 354.122 6 3825.204 384.7 343.4 7 8868.753 547.74 317.747 7 4452.3 405.8 182.3 8 9541.394 575.856 246.784 8 4463.52 406.6 182.3 9 10005.08 603.972 140.996 9 7092.06 499.2 333.8 10 10133.46 618.03 74.806 10 7169.58 503.3 98.7 11 10166.97 625.059 38.494 11 9093.3 546.6 399.9 12 10184.7 632.088 7.87 12 9835.86 595.2 399.9 13 10406.04 632.089 7.87 13 10315.26 630.8 5.2 14 10406.05 632.09 7.406 14 10330.56 663.7 7.9 15 11401.67 1000 7.406 15 11549.46 1000 7.406 Table lb Table lb OSG Thin Metal RSG Thin Metal Mass x Cp Liquid Volume Mass x Cp Liquid Volume (BT.U/°F) (Cu ft) (BTU/°F) (Cu ft) 0 0 0 0 26345.28 1993.73 6929.47 4463.52 40171.28 3349.57 31238.86 9835.86 67670.64 8116.73 81368.14 10184.7

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Page 7 of 27 Table Ic Table Ic OSG Sensible Heat and SG Energy RSG Sensible Heat and SG Energy (LOCA hot leg break at full power) (LOCA hot leg break at full power)

Time Energy Rate Time Energy Rate (seconds) (BTU/hour) (seconds) (BTU/hour) 1.2200E+01 2.86825E+09 1.2500E+01 1.0882E+10 2.2200E+01 2.86461E+09 1.4020E+01 1.0627E+10 H 3.2200E+01 1.00942E+09 1.4520E+01 9.3675E+09 4.7200E+01 9.33001E+08 1.6020E+01 9.0620E+09 5.7200E+01 6.33103E+08 1.6520E+01 3.0927E+09 1.4720E+02 6.23452E+08 1.7020E+01 2.8962E+09 1.5220E+02 2.98048E+08 2.6520E+01 2.8934E+09 1.8720E+02 2.95063E+08 2.7020E+01 1.3883E+/-09 1.9220E+02 1.72512E+07 5.3020E+01 8.0406E+08 3.9720E+02 7.53696E+06 6.8520E+01 6.4061E+08 9.4300E+02 3.14460E+06 1.4752E+02 6.2632E+08 1.2430E+03 3.19536E+06 1.6302E+02 3.0109E+08 5.0860E+03 1.28664E+06 1.7902E+02 2.9892E+08 1.4086E+04 3.16800E+05 1.9452E+02 2.1003E+07 3.2860E+04 2.04120E+05 4.7802E+02 5.2961E+06 5.2860E+04 1.02600E+05 6.9002E+02 3.1698E+06 8.8860E+04 5.79600E+04 6.5000E+03 9.5591 E+05 1.9886E+05 1.90800E+04 3.9800E+04 1.5394E+05 2.9686E+05 1. 18800E+04 8.7800E+04 6.1848E+04 7.8715E+05 6.84000E+03 1.4000E+06 1.9188E+03 1.22715E+06 1.80000E+03 2.OOOOE+07 1.2240E+02 3.25215E+06 5.40000E+02 1.00001 E+07 5.40000E+02

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Page 8 of 27 Table Id Table Id OSG Mass-Energy Release RSG Mass-Energy Release (LOCA hot leg break at full Dower) (LOCA hot leg break at full nower)

Mass Flow Mass Flow Time Rate Enthalpy Time Rate Enthalpy (seconds) (Ibm/hour) (BTU/lbm) (seconds) (Ibm/hour) (BTU/lbm) 0.00000E+00 0.00000E+00 0.00 0.OOE+00 0.OOOOOE+00 641.23 1.03421E-02 6.27354E+08 643.05 1.03E-02 6.22255E+08 641.23 2.02421E-02 6.02244E+08 640.94 2.02E-02 5.99190E+08 639.22 3.07891E-02 6.08616E+08 642.24 3.06E-02 6.05150E+08 640.55 4.01493E-02 5.48352E+08 641.28 4.OOE-02 5.41852E+08 639.41 4.99552E-02 4.76899E+08 638.15 5.06E-02 4.73380E+08 635.80 5.99552E-02 4.95108E+08 637.33 6.06E-02 5.03060E+08 636.52 6.99552E-02 5.28664E+08 640.99 7.06E-02 5.27155E+08 639.54 7.99552E-02 5.06801E+08 640.93 8.06E-02 5.00408E+08 638.88 8.99552E-02 4.99086E+08 639.35 9.06E-02 5.00633E+08 637.67 9.99552E-02 5.29254E+08 640.78 1.OIE-01 5.30261E+08 639.56 1.49955E-01 5.09058E+08 641.86 1.5 1E-01 4.99232E+08 640.22 1.99955E-01 4.72468E+08 641.13 2.01E-01 4.75776E+08 640.22 2.49955E-01 4.53560E+08 640.96 2.51E-01 4.51020E+08 639.95 2.99955E-01 4.26856E+08 639.77 3.01E-01 4.28538E+08 639.18 3.49955E-01 4.19393E+08 638.70 3.51E-01 4.21443E+08 638.37 3.99955E-01 4.06228E+08 637.33 4.01E-01 4.08901E+08 637.08 4.49955E-01 3.93149E+08 636.55 4.5 1E-0I 3.96835E+08 636.54 4.99955E-0I 3.85862E+08 635.72 5.01E-01 3.88010E+08 636.21 9.99955E-0l 2.88242E+08 645.34 6.01E-01 3.68273E+08 635.77 1.49996E+00 2.64587E+08 630.78 7.01E-01 3.47380E+08 637.02 1.99996E+00 2.66148E+08 611.46 8.01E-01 3.24827E+08 639.55 2.49996E+00 2.46600E+08 611.91 9.01E-01 3.05871E+08 643.57 2.99996E+00 2.20959E+08 628.09 1.OOE+00 2.91936E+08 647.65 4.00168E+00 1.88085E+08 635.67 2.OOE+00 2.64152E+08 618.34 5.00168E+00 1.62186E+08 642.94 3.OOE+00 2.31026E+08 622.43 6.00168E+00 1.26314E+08 668.96 4.OOE+00 1.94832E+08 632.64 7.00322E+00 6.26681E+07 933.15 5.OOE+00 1.70660E+08 634.11 8.00322E+00 4.88578E+07 923.82 6.OOE+00 1.37254E+08 654.53 9.00322E+00 2.30701E+07 1111.97 7.OOE+00 7.56652E+07 820.79 1.00024E+-01 2.41007E+07 981.82 8.OOE+00 5.11953E+07 941.15 1.02024E+01 2.23662E+07 1006.48 9.OOE+00 3.36803E+07 1007.08 1.04024E+01 2.02257E+07 1021.58 1.OOE+01 2.10704E+07 1033.84 1.06024E+01 1.73485E+07 1034.34 1.1OE+0I 1.61884E+07 1024.61 1.08024E+01 1.23247E+07 1100.95 1.11E++/-0 1.39168E+07 1044.96 1.10024E+01 7.76318E+06 1207.09 1.12E+01 1.08963E+07 1103.07 1.11999E+01 5.11481E+06 1225.42 1.13E+01 8.46398E+06 1189.23 1.14035E+01 4.37044E+06 1233.57 1.14E+01 . 6.83319E+06 1210.13 1.16035E+01 3.80862E+06 1226.16 1.15E+0I 5.46634E+06 1219.13 1.18035E+01 3.16153E+06 1228.38 1.16E+01 4.26678E+06 1224.78 1.20019E+01 2.49742E+06 1229.31 1.17E+01I 3.77926E+06 1231.33

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Page 9 of 27 Table Id Table Id OSG Mass-Energy Release RSG Mass-Energy Release (LOCA hot leg break at full power) (LOCA hot leg break at full power)

Mass Flow Mass Flow Time Rate Enthalpy Time Rate Enthalpy (seconds) (Ibm/hour) (BTU/Ibm) (seconds) (Ibm/hour) (BTU/lbm) 1.22000E+01 0.OOOOOE+00 1229.31 1.18E+01 3.52307E+06 1230.57 1.00001E+07 0.OOOOOE+00 0.00 1.19E+01 3.20883E+06 1225.68 1.20E+01 2.90038E+06 1227.30 1.21E+01 2.53292E+06 1228.09 1.22E+01 2.26622E+06 1227.03 1.23E+01 1.90522E+06 1228.18 1.24E+01 1.59699E+06 1228.04 1.25E+01 0.00000E+00 1228.04 2.OOE+07 0.OOOOOE+00 0.00 Table le Table le OSG Mass-Energy Release RSG Mass-Energy Release (MSLB MSIV Failure at full power) (MSLB MSIV Failure at full power)

Mass Flow Mass Flow Time Rate Enthalpy Time Rate Enthalpy (seconds) (Ibm/hour) (BTU/lbm) (seconds) (Ibm/hour) (BTU/lbm) 0.00 5.98327E+07 1195.73 0.00 4.48240E+07 1197.57 0.10 5.75122E+07 1196.41 0.10 4.14022E+07 1199.24 0.20 5.57370E+07 1197.03 0.20 3.87374E+07 1200.21 0.30 5.43010E+07 1197.60 0.30 3.66149E+07 1200.74 0.40 5.30896E+07 1198.12 0.40 3.48771E+07 1201.00 0.50 5.20330E+07 1198.61 0.50 3.34104E+07 1201.09 0.60 5.10912E+07 1199.06 0.60 3.21755E+07 1201.09 0.70 5.02333E+07 1199.48 0.70 3.11522E+07 1201.04 0.80 4.94377E+07 1199.87 0.80 3.02992E+07 1200.97 0.90 4.86918E+07 1200.24 0.90 2.95832E+07 1200.90 1.00 4.79844E+07 1200.58 1.00 2.89779E+07 1200.83 1.99 4.22996E+07 1202.77 1.98 2.59308E+07 1200.71 2.99 3.84905E+07 1203.67 2.98 2.60175E+07 1201.60 3.99 3.57314E+07 1204.14 3.98 2.60948E+07 1202.24 4.99 3.36987E+07 1204.38 4.98 2.56803E+07 1202.54 5.99 3.22780E+07 1204.49 5.98 2.48926E+07 1202.61 6.99 3.12150E+07 1204.54 6.98 2.32135E+07 1202.23 7.99 3.02679E+07 1204.56 7.98 2.11898E+07 1201.49 8.99 2.90136E+07 1204.56 8.98 1.91308E+07 1200.62 9.99 2.72875E+07 1204.41 9.98 1.73553E+07 1199.93 10.99 2.52859E+07 1204.10 10.98 1.59664E+07 1199.48 11.99 2.31050E+07 1203.71 11.98 1.45819E+07 1199.96 12.99 2.14734E+07 1203.29 12.98 1.37377E+07 1200.68 13.99 2.02301E+07 1202.88 13.98 1.31289E+07 1201.39 14.99 1.92300E+07 1202.46 14.98 1.26752E+07 1201.97

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Page 10 of 27 Table le Table le OSG Mass-Energy Release RSG Mass-Energy Release (MSLB MSIV Failure at full power) (MSLB MSIV Failure at full power)

Mass Flow Mass Flow Time Rate Enthalpy Time Rate Enthalpy (seconds) (Ibm/hour) (BTU/lbm) (seconds) (Ibm/hour) (BTU/lbm) 15.99 1.83844E+07 1202.05 15.98 1.21283E+07 1202.86 16.99 1.76321E+07 1201.62 16.98 1.14678E+07 1204.18 17.99 1.69480E+07 1201.18 17.98 1.12155E+07 1204.36 18.99 1.63347E+07 1200.76 18.98 1.09884E+07 1204.43 19.99 1.57910E+07 1200.37 19.98 1.07663E+07 1204.49 20.99 1.53147E+07 1200.00 20.98 1.05641E+07 1204.53 21.99 1.48990E+07 1199.67 21.98 1.03825E+07 1204.56 22.99 1.45314E+07 1199.34 22.98 1.02159E+07 1204.58 23.99 1.41958E+07 1199.02 23.98 1.00561E+07 1204.59 24.99 1.38684E+07 1198.69 24.98 9.89716E+06 1204.60 25.99 1.35715E+07 1198.37 25.98 9.73782E+06 1204.59 26.99 1.32724E+07 1198.05 26.98 9.58122E+06 1204.58 27.99 1.29986E+07 1197.76 27.98 9.43218E+06 1204.56 28.99 1.27477E+07 1197.47 28.98 9.29434E+06 1204.54 29.99 1.24979E+07 1197.16 29.98 9.16805E+06 1204.51 30.99 1.22491E+07 1196.85 30.98 9.05065E+06 1204.48 31.99 1.20009E+07 1196.52 31.98 8.93819E+06 1204.45 32.99 1.17508E+07 1196.18 32.98 8.82752E+06 1204.41 33.99 1.15086E+07 1195.83 33.98 8.71765E+06 1204.37 34.99 1.12624E+07- 1195.47 34.98 8.56868E+06 1204.30 35.99 1.10236E+07 1195.12 35.98 8.42364E+06 1204.23 36.99 1.07968E+07 1194.78 36.98 8.29930E+06 1204.17 37.99 1.05819E+07 1194.45 37.98 8.18399E+06 1204.10 38.99 1.03779E+07 1194.12 38.98 8.07343E+/-06 1204.03 39.99 1.09174E+07 1193.56 39.98 7.96579E+06 1203.95 40.99 1.00225E+07 1193.42 40.98 7.86085E+06 1203.87 41.99 9.70326E+06 1193.14 41.98 7.75912E+06 1203.80 42.99 9.52574E+06 1192.81 42.98 7.66116E+06 1203.71 43.99 9.35935E+06 1192.48 43.98 7.56695E+06 1203.63 44.99 9.18911EE+06 1192.16 44.98 7.47580E+06 1203.55 45.99 9.01588E+06 1191.85 45.98 7.38673E+06 1203.46 46.99 8.89207E+06 1191.53 46.98 7.29889E+06 1203.37 47.99 8.73400E+06 1191.22 47.98 7.21192E+06 1203.28 48.98 8.58726E+06 1190.91 48.98 7.12598E+06 1203.18 49.99 8.45867E+06 1190.60 49.98 7.04156E+06 1203.08 50.99 8.32622E+06 1190.30 50.98 6.95905E+06 1202.98 51.99 8.19641E+06 1190.00 51.98 6.87870E+06 1202.88 52.99 3.65717E+06 1184.74 52.98 6.80026E+06 1202.78 53.99 6.83237E+05 1182.70 53.98 6.72340E+06 1202.68 54.99 3.68528E+05 1182.53 54.98 6.64772E+06 1202.57 55.99 6.18599E+05 1191.10 55.98 6.57302E+06 1202.46 56.99 3.37910E+05 1208.76 56.98 6.49933E+06 1202.35

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Page 11 of 27 Table le Table Ie OSG Mass-Energy Release RSG Mass-Energy Release (MSLB MSIV Failure at full power) (MSILB MSTV Failure at full nower/

Mass Flow Mass Flow Time Rate Enthalpy Time Rate Enthalpy (seconds) (Ibm/hour) (BTU/lbm) (seconds) (Ibm/hour) (BTU/Ibm) 57.99 2.69605E+05 1221.42 57.98 6.42683E+06 1202.24 58.99 1.36503E+05 1236.78 58.98 6.35576E+06 1202.12 59.99 1.02371E+05 1241.74 59.98 6.28628E+06 1202.01 60.99 8.92084E+04 1245.39 60.98 6.21832E+06 1201.89 61.99 8.08884E+04 1248.49 61.98 6.15172E+06 1201.78 62.99 6.97244E+04 1251.03 62.98 6.08627E+06 1201.66 63.99 5.55962E+04 1252.71 63.98 6.02190E+06 1201.54 64.99 4.26834E+04 1253.43 64.98 5.95854E+06 1201.42 65.99 3.53102E+04 1253.42 65.98 5.89705E+06 1201.30 66.99 3.50379E+04 1253.14 66.98 5.83906E+06 1201.18 67.99 4.00255E+04 1253.08 67.98 5.78383E+06 1201.07 68.99 4.61833E+04 1253.07 68.98 5.73088E+06 1200.96 69.99 4.95709E+04 1254.27 69.98 5.67983E+06 1200.85 70.99 4.83487E+04 1255.18 70.98 5.63051E+06 1200.74 71.99 4.34754E+04 1255.89 71.98 5.58259E+06 1200.63 72.99 3.77662E+04 1256.19 72.98 5.53590E+06 1200.53 73.99 3.40761E+04 1256.14 73.98 5.49022E+06 1200.42 74.99 3.37815E+04 1255.94 74.98 5.44540E+06 1200.31 75.99 3.62981E+04 1255.86 75.98 5.40148E+06 1200.21 76.99 3.96734E+04 1256.04 76.98 5.35540E+06 1200.09 77.99 4.17902E+04 1256.47 77.98 5.29499E+06 1199.94 78.99 4.15062E+04 1257.01 78.98 5.21809E+06 1199.74 79.99 3.91316E+04 1257.46 79.98 5.12838E+06 1199.51 80.99 3.60540E+04 1257.69 80.98 5.02981E+06 1199.23 81.99 3.38323E+04 1257.73 81.98 4.92505E+06 1198.93 82.99 2.15769E+04 1257.79 82.98 4.81594E+06 1198.60 83.99 1.68380E+04 1258.41 83.98 4.70243E+06 1198.24 84.99 1.58215E+04 1258.82 84.98 4.58420E+06 1197.87 85.99 1.57703E+04 1259.21 85.98 4.46616E+06 1197.48 86.99 1.52111E+04 1259.59 86.98 4.34894E+06 1197.07 87.99 1.38181E+04 1259.91 87.98 4.23263E+06 1196.65 88.99 1.20753E+04 1260.10 88.98 4.11664E+06 1196.21 89.99 1.07364E+04 1260.16 89.98 4.00036E+06 1195.74 90.99 1.03087E+04 1260.15 90.98 3.88346E+06 1195.25 91.99 1.07857E+04 1260.16 91.98 3.76603E+06 1194.73 92.99 1.17064E+04 1260.24 92.98 3.64831E+06 1194.19 93.99 1.24519E+04 1260.40 93.98 3.53084E+06 1193.62 94.99 1.25882E+04 1260.62 94.98 3.41410E+06 1193.02 95.99 1.20720E+04 1260.82 95.98 3.29841E+06 1192.40 96.99 1.12037E+04 1260.97 96.98 3.18362E+06 1191.74 97.99 1.04381E+04 1261.05 97.98 3.06965E+06 1191.06 98.99 1.01073E+04 1261.10 98.98 2.95649E+06 1190.34

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Page 12 of 27 Table le Table le OSG Mass-Energy Release RSG Mass-Energy Release (MSLB MSIV Failure at full power) (MSLB MSIV Failure at full power)

Mass Flow Mass Flow Time Rate Enthalpy Time Rate Enthalpy (seconds) (Ibm/hour) (BTU/Ibm) (seconds) (Ibm/hour) (BTU/lbm) 99.99 1.02701E+04 1261.14 99.98 2.84427E+06 1189.59 104.95 1.05164E+04 1261.79 104.90 2.33040E+06 1185.37 109.95 1.01719E+04 1262.22 109.90 1.87114E+06 1179.94 114.95 9.42246E+03 1262.79 114.90 1.16445E+06 1177.47 119.95 9.40644E+03 1263.28 119.90 8.10223E+05 1177.11 124.95 8.89672E+03 1263.76 124.90 5.39881E+05 1176.82 129.95 8.63748E+03 1264.26 129.90 3.42639E+05 1176.59 134.95 8.38825E+03 1264.73 134.90 1.46046E+05 1238.51 139.95 8.07574E+03 1265.20 139.90 1.58614E+04 1256.77 144.95 7.86686E+03 1265.66 144.90 1.14422E+04 1258.01 149.95 7.62509E+03 1266.11 149.90 1.06888E+04 1258.58 154.99 7.41622E+03 1266.56 154.90 1.00732E+04 1259.14 159.95 7.24896E+03 1267.00 159.90 9.73022E+03 1259.64 164.95 7.06982E+03 1267.44 164.90 9.23760E+03 1260.13 169.95 6.90764E+03 1267.87 169.90 8.89366E+03 1260.62 174.95 6.74752E+03 1268.30 174.90 8.54284E+03 1261L08 179.95 6.59416E+03 1268.72 179.90 8.20044E+03 1261.55 184.95. 6.44746E+03 1269.14 184.90 7.91428E+03 1262.00 189.95 6.30508E+03 1269.56 189.90 7.61573E+03 1262.45 194.95 6.16925E+03 1269.97 194.90 7.35336E+03 1262.90 199.95 6.03828E+03 1270.38 199.90 7.10273E+03 1263.33 200.00 6.03702E+03 1270.38 200.00 7.09805E+03 1263.34 200.00 0.OOOOOE+00 0.00 200.00 0.OOOOOE+00 0.00 2.OE+07 0.OOOOOE+00 0.00 2.OE+07 0.OOOOOE+00 0.00

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Page 13 of 27 Response to RAI 2 RAI 2: Section 4.2.3.1 states that the methodology used in the new evaluation is identical to the methodology used in the current licensing basis evaluation of the SONGS 2 and 3, and that only input parameters have been updated. Other than input parameter changes required by the differences between the RSGs and existing SGs (as would be included in the response to the RAI above), what other input parameters have been updated and why are they updated? Please explain how the updated parameters are still expected to yield conservative results?

Response 2: Table 2 provides the analysis input parameter changes that are not due to RSG design differences. Table 2 addresses changes relative to the mass-energy release and containment pressure-temperature response analyses previously reviewed by the NRC Staff as part of PCN-528 (approved as U2/U3 License Amendments 182/173, dated January 24, 2002). The response to RAI 1 provides the input parameter changes that are due to steam generator design differences..

Table 2: Analysis Input Parameter Changes not due to RSG Design Changes ITEM I PARAMETER OSG VALUE RSG VALUE COMMENTS I Shutdown Cooling 3.0 E6 lb/hr 2.732 E6 lb/hr Subsequent to-Heat Exchanger PCN-528, the OSG (SDCHX) CCW flow rate Component Cooling through the SDCHX Water (CCW) flow was reduced to rate, as modeled in provide margin to the LOCA containment high flow related P-T response erosion and flow analyses. induced vibration design limits. This change was implemented in the OSG analysis subsequent to PCN-528 approval using the 10CFR50.59 process.

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Page 14 of 27 ITEM PARAMETER OSG VALUE RSG VALUE I COMMENTS 2 Decay Heat versus Various values Various values The decay heat values Time table, as are essentially the modeled in LOCA (10 second value was (10 second value was same. The minor containment P-T 1.40669 E9 BTU/hr.) 1,.40640 E9 BTU/hr.) differences between response analyses. the two sets of data (as evidenced by the noted 10 second value) are due to a slight difference in the modeled initial power plus uncertainty and round-off in the MW to BTU/hr conversion factor.

3 Containment Spray CSS flow rate starts CSS flow rate starts CSS Injection phase System (CSS) to ramp up at 33 to ramp up at 34 design flow rate is Flowrate and Timing, seconds and goes seconds and goes 1606 gpm. Use of a as modeled in LOCA from 0 to 1600 gpm from 0 to 1565 gpm lower flow rate containment P-T in the following 27 in the following 27 conservatively response analyses. seconds. At 60 seconds. At 61 addresses reduced seconds a steady state seconds a steady state CSS effectiveness ,

1600 gpm flowrate is 1565 gpm flowrate is should there be future reached and reached and CSS flow rate maintained maintained degradation.

throughout the throughout the injection phase. injection phase. The 1 second flow start time delay is discretionary margin that was conservatively added to the RSG LOCA analysis.

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Page 15 of 27 ITEM PARAMETER OSG VALUE RSG VALUE COMMENTS 4 Containment Spray CSS flow rate starts CSS flow rate starts CSS Injection phase System (CSS) to ramp up at 23 to ramp up at 28 design flow rate is Flowrate and Timing, seconds and goes seconds and goes 1606 gpm. Use of a as modeled in MSLB from 0 to 1600 gpm from 0 to 1565 gpm lower flow rate containment P-T in the following 27 in the following 27 conservatively response analyses. seconds. At 50 seconds. At 55 addresses reduced seconds a steady state seconds a steady state CSS effectiveness 1600 gpm flowrate is 1565 gpm flowrate is should there be future reached and reached and CSS flow rate maintained maintained degradation.

throughout the throughout the injection phase. injection phase. The 5 second flow start delay for RSG is to bound a slightly longer delay in reaching the Containment Spray Actuation Signal setpoint, due to a slower containment pressure buildup associated with reduced M-E release rate out of the RSG exit nozzle flow restrictor.

5 Nitrogen Release 3576 Ibm between 90 5519 Ibm between 90 RSG input from Safety Injection and 100 seconds and 100 seconds ' conservatively Tanks (SIT), as following start of the following start of the releases all SIT modeled in LOCA LOCA LOCA nitrogen into containment P-T containment in the 10 response analyses second period of interest. No impact on limiting case peak containment pressure or temperature, which occur prior to SIT discharge.

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Page 16 of 27 ITEM PARAMETER OSG VALUE RSG VALUE COMMENTS 6 ECU heat removal Various MSLB Various MSLB and Subsequent to capability as a values based on LOCA values based PCN-528, the OSG function of 100% of design ECU on approximately minimum CCW flow containment Heat Removal Rate. 93% of design ECU rate through the ECU atmosphere saturation Heat Removal Rate. and the ECU heat temperature, as Various LOCA removal rate were modeled in LOCA values based on 98% Example value: at reduced to reflect and MSLB of design ECU Heat 300F heat removal post-RAS flow containment P-T Removal Rate. rate was 45.4E6 reduction if CCW response analyses BTU/hr which is 93% flow is also aligned to Example value: at of original design the SFP Cooling heat 300F heat removal value, 48.82E6 exchanger and to rate was 47.844E6 Btu/hr. provide margin to the BTU/hr which is 98% high flow related of original design erosion and flow value, 48.82E6 induced vibration Btu/hr. design limits. This change was implemented in the OSG analysis subsequent to PCN-528 approval using the S1OCFR50.59 process.

7 CSS spray efficiency Various values - Various values - Minor differences as a function of the Data extracted from a BN-TOP-3 plot data. with no significant containment water plot provided in as tabulated in changes to CSS vapor to air mass Bechtel COPATTA Bechtel Design Guide efficiencies.

ratio, as modeled in topical report 3DG-N30-001 Rev 2 LOCA and MSLB BN-TOP-3 Rev 4 December 1995 The RSG data uses containment P-T March 1983 tabulated Design response analyses Guide 3DG-N30-001 data, which is the same data in BN-TOP-3, but in tabular form.

8 Containment Spray MSLB: Steady state MSLB: Steady state The RSG delay System (CSS) Pre- flowrate: 1600 gpm flowrate: 1600 gpm addresses additional RAS Phase Flowrate per train. Timing: per train. Timing: 30 diesel generator and Timing, as 46.9 sec. delay after sec. delay after starting time delay modeled in LOCA reaching CTMNT reaching CTMNT associated with a and MSLB M-E pressure of 20.0 psig pressure of 20.0 psig potential future release analyses. Technical LOCA: Steady state LOCA: Steady state Specification change.

flowrate: 1600 gpm flowrate: 1600 gpm per train. Timing: per train. Timing: This parameter has no 57.9 sec. delay after 60.4 sec. delay after effect on the M&E reaching CTMNT reaching CTMNT releases, which are pressure of 5.0 psig pressure of 5.0 psig. based on the critical flow tables.

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Page 17 of 27 ITEM I PARAMETER OSG VALUE RSG VALUE COMMENTS 9 Containment Air OSG LOCA M-E was LOCA M-E data is Use of a lower heat Emergency Cooling modeled as 100% of based on 94% of removal rate in RSG Unit (ECU) heat design basis ECU design basis ECU analyses removal capability as heat removal heat removal conservatively a function of capability. capability, addresses reduced containment ECU effectiveness atmosphere saturation with reduced temperature, as Component Cooling modeled in LOCA Water System flow M-E release analyses rate.

10 Heat sink input, Various values Various values The RSG heat sink including number of model is the same as heat sinks, material currently used for the thickness, surface OSG. This heat sink area, thermal model has been properties, and updated since the nodalization (wall PCN-528 T-cold segments), as license amendment modeled in LOCA request to reflect heat and MSLB M-E sink changes made release analyses and via the IOCFR50.59 containment P-T process.

response analyses.

11 Initial partial pressure 16.915 15.1 The RSG maximum of air, psia initial containment pressure was revised Initial partial pressure 0.085 1.7 to be consistent with of steam, psia the containment P-T response analysis Initial containment 17.0 16.8 input data.

pressure, psia The RSG partial All parameters are as pressures reflect an modeled in MSLB increase in assumed M-E release analyses initial containment humidity from 50%

to 100%.

Containment parameters are only used to establish the time the high containment pressure reactor trip condition is reached. The humidity value has negligible effect on the time to trip the reactor.

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Page 18 of 27 ITEM PARAMETER OSG VALUE RSG VALUE COMMENTS 12 Fan Cooler actuation MSLB: 37.0 sec. MSLB: 37.0 sec. MSLB: The RSG fan condition, as modeled delay after reaching delay after reaching cooler actuation in LOCA and MSLB CTMNT pressure of CTMNT pressure of pressure was M-E release analyses 5.0 psig 6.0 psig increased by I psi to approximate a LOCA: 48 sec. delay LOCA: 51.8 sec. potential 1 second after reaching delay after reaching signal processing CTMNT pressure of CTMNT pressure of delay.

5.0 psig. 5.0 psig.

LOCA: The RSG delay addresses additional diesel generator starting time delay associated with a potential future Tech Spec change.

13 Core Thermal Power, 3390.0 3438.0 U2/U3 License MWt, as modeled in Amendments 180/171 LOCA and MSLB granted exemption to M-E release analyses IOCFR50 Appendix K, and authorized Values of power 1.02 1.0058 increase in rated demand (fraction of thermal power.

full load), initial power fraction, and Note that with power fractional turbine measurement admission valve area uncertainty, 3390 vs. time, as modeled MW plus 2%

in LOCA and MSLB uncertainty is M-E release analyses. essentially the same as 3438 MW plus 0.58% uncertainty.

14 Overall Heat Transfer 6.0305 E6 6.071916 E6 Recalculation of the Coefficient Fuel fuel heat transfer Region 1 to 2, Btu/hr- coefficients to correct

'F, as modeled in minor errors in MSLB M-E release calculated fuel region analyses total fuel energy and fuel region Overall Heat Transfer 2.5292 E7 2.5692641 E7 temperature, resulting Coefficient, Fuel in a minor increase in Region 2 to Coolant, the fuel heat transfer Btu/hr-°F, as modeled rates.

in MSLB M-E release analyses

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Page 19 of 27 ITEM PARAMETER OSG VALUE RSG VALUE COMMENTS 15 MSIV closure A total of 8.0 seconds A total of 15.1 The time to close the position versus time, to close, modeled seconds to close, MSIVs increased to as modeled in MSLB over 18 time steps modeled over 21 time 13.5 seconds (for an M-E release analyses steps inside containment MSLB) and to 15.1 seconds (for an outside containment MSLB) to reflect the closure profile of the MSIV valve type.

This change was implemented for the OSG analysis under the 10CFR50.59 process subsequent to NRC Staff review of PCN-528 (approved as U2/U3 License Amendments 182/173). Modeling 15.1 seconds rather than 13.5 seconds conservatively results in a minor increase in the M-E release.

16 Pressurizer water 750.0 at all powers 798.4 at all powers The methodology volume vs. power, ft3, does not consider as modeled in MSLB RCS pressure M-E release analyses changes, so the pressurizer water volume (level) input parameter has no effect on the analysis.

OSG volume was arbitrarily selected.

RSG volume was arbitrarily set at nominal conditions.

17 Fuel centerline see Table 2a see Table 2a The fuel centerline temperature vs. temperature was Power (kW/ft), as updated to be modeled in LOCA consistent with the M-E release analyses. current fuel design.

18 Fuel thermal Thermal conductivity Thermal conductivity The thermal conductivity and see Table 2b see Table 2b conductivity volumetric heat (coefficients) and capacity to account Volumetric heat Volumetric heat volumetric heat for the fuel and fill capacity capacity capacity were gas compositions, as b [ ' updated to be modeled in LOCA consistent with the M-E release analyses. current fuel design and fill gas compositions,

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Page 20 of 27 ITEM I PARAMETER OSG VALUE RSG VALUE COMMENTS 19 Reactivity insertion see Table 2c see Table 2c The Doppler and Doppler reactivity was reactivity vs. Fuel updated to be temperature, as consistent with the modeled in LOCA current fuel design.

M-E release analyses.

20 Appropriate changes Various values Various values The different to the input thermal-hydraulic parameters affected conditions at the end by the results of the of blowdown phase blowdown mass & impact several input energy release parameters during the analysis, as modeled reflood/post-reflood in LOCA M-E release phase.

analyses.

21 Heat transfer 196.0 BTU/hr-ft 2-OF 171.0 BTU/hr-ft2 -OF Use of the heat coefficient for the (pump suction leg transfer coefficient secondary side of the break) calculated specific to SG, as modeled in the break location is LOCA M-E release 136.0 BTU/hr-ft2'-F appropriate.

analyses (pump discharge leg break) 22 Input.paramreters Various values Various values The different affected by the results thermal-hydraulic of the blowdown conditions at the end mass & energy of blowdown and release analysis, as reflood/post-reflood modeled in LOCA phases impact several M-E release analyses. input parameters during the long term boil-off phase.

23 ECU heat removal see Table 2d see Table 2d The reduced capability as a Emergency Cooling function of Unit (ECU) heat containment removal capacity was atmosphere saturation used throughout the temperature, as accident to account modeled in LOCA for reduction in the M-E release analyses heat removal capacity due to post-accident alignment of the Spent Fuel Pool Heat Exchanger (SFPHX) rather than after the SFPHX is aligned.

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Page 21 of 27 ITEM I PARAMETER OSG VALUE RSG VALUE COMMENTS 24 Values of fractional 1.75 1.71 OSG and RSG value FW flow to the of 1.71 was ruptured SG vs. time conservatively (MSIV Failure event modeled in the OSG at full power). analysis as 1.75 (i.e.,

Nominal steady state all of the flow to the fractional flow = 1.0 ruptured SG, and per SG, or 2.0 for 75% of the flow to both SGs, as modeled the intact SG is in MSLB M-E release directed to the analyses. ruptured SG and is available for release from the ruptured OSG).

25 Values of fractional 0.25 0.302 OSG and RSG value FW flow to intact SG is actually 0.29 versus time (MSIV (representing total Failure event at full fractional flow of 2.0 power). Nominal less 1.71 flowto steady state fractional ruptured SG per Item flow = 1.0 per SG, or 21).

2.0 for both SGs, as modeled in MSLB OSG was modeled as M-E release analyses. 0.25 for consistency with the conservatively high 1.75 fractional flow to ruptured OSG of Item 21 (i.e., total fractional FW flow is 2.0).

RSG was conservatively modeled as 0.302 (i.e., more FW mass flow into the intact RSG).

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Page 22 of 27 c

Table 2a Table 2a OSG Fuel Centerline Temperature vs. RSG Fuel Centerline Temperature vs.

Power Power Axial Node Centerline Power Axial Node Centerline Power Temperature Temperature (OF) (kw/ft) (OF) (kw/ft) b,c Table 2b Table 2b OSG Fuel Thermal Conductivity (Btu/hr-ft-0 F) RSG Fuel Thermal Conductivity (Btu/hr-ft-°F)

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Page 23 of 27 Table 2c Table 2c OSG Doppler Reactivity vs. Fuel RSG Doppler Reactivity vs. Fuel Temperature Temperature Doppler Reactivity Temperature Doppler Reactivity Temperature (Ap) (OF) (Ap) (OF) 0.00000 0.0 0.00000 0.0 0.03037 200.0 0.03049 200.0 0.02467 400.0 0.02455 400.0 0.01951 600.0 0.01921 600.0 0.01477 800.0 0.01437 800.0 0.01037 1000.0 0.00991 1000.0 0.00626 1200.0 0.00577 1200.0 0.00235 1400.0 1400.0

__ 1500.0 0.00001 1500.0

-0.00135 1600.0 -0.00181 1600.0

-0.00490 1800.0 -0.00534 1800.0

-0.00820 2000.0 -0.00871 2000.0

-0.01150 2200.0 -0.01196 2200.0

-0.01460 2400.0 -0.01510 2400.0

-0.01750 2600.0 -0.01812 2600.0

-0.02300 3000.0 -0.02387 3000.0

-0.03630 4000.0 -0.03693 4000.0

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Page 24 of 27 Table 2d Table 2d OSG ECU Heat Removal Rate vs. RSG ECU Heat Removal Rate vs.

Containment Atmosphere Saturation Containment Atmosphere Saturation Temperature Temperature Heat Removal Rate Temperature Heat Removal Rate Temperature (BTU/sec) (OF) (BTU/sec) (OF) 0.00 105.0 0.00 105.0 463.89 120.0 436.06 120.0 838.89 130.0 788.56 130.0 1269.44 140.0 1193.28 140.0 1755.56 150.0 1650.22 150.0 2297.22 160.0 2159.39 160.0 2888.89 170.0 2715.56 170.0 3536.11 180.0 3323.94 180.0

.4230.56 190.0 3976.72 190.0 4966.67 200.0 4668.67 200.0 5744.44 210.0 5399.78 210.0 6558.33 220.0 6164.83 220.0 7400.00 230.0 6956.00 230.0 8261.11 240.0 7765.44 240.0 9141.67 250.0 8593.17 250.0 10030.56 260.0 9428.72 260.0 10919.44 270.0 10264.28 270.0 11811.11 280.0 11102.44 280.0 13561.11 300.0 12747.44 300.0

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Page 25 of 27 Response to RAI 3 RAI 3: Tables 4.2-1 and 4.2-3 provided a summary of significant inputs, significant points of methodology, and assumptions for LOCA and MSLB respectively.

Please indicate if all of them are the same between the existing and new analyses with the exception of differences dictated by the SG change out, and if they are different, explain the reasons for the difference and how they would still provide conservative results.

Response 3: Table 3 provides the items that differ between Replacement Steam Generator (RSG) and Original Steam Generator (OSG) analyses relative to the summary of significant inputs, significant points of methodology, and assumptions identified in LAR Tables 4.2-1 (LOCA) and 4.2-3 (MSLB). Items listed in LAR Tables 4.2-1 and 4.2-3, but not included in Table 3, are items that did not differ between RSG and OSG analyses.

Table 3: Mass-Energy Significant Inputs, Points of Methodology, and Assumptions That Differ Between RSG and OSG Item RSG discussion per LAR Comments Table 4.2-1, Main feedwater prior to feedwater pump trip and the The OSG and RSG modeling of main-feedwater LOCA inventory in the feedwater lines downstream of the flow is the same. However, the main feedwater Sources of feedwater isolation valves after feedwater pump flow description provided in the license amendment Energy trip. request is inaccurate. The proper description should state that the main feedwater inventory in the feedwater lines is a source of energy prior to the closure of the Main Feedwater Isolation Valves (MFIVs).

Table 4.2-3, No tube plugging is assumed when generating mass The RSG analysis minimizes tube plugging by MSLB 5 and energy for steam line breaks. Less active tube assuming no tube plugging, because initially there area reduces primary to secondary heat transfer area are no tubes plugged in the new RSGs. The OSG and thus slows the heat addition to the secondary analysis also minimizes tube plugging, but models inventory. 425 plugged tubes because at the time the OSG analysis was originated, at least 425 tubes were plugged.

Table 4.2-3, The evaluation of a 20 MW return to power The RSG Post-Trip Steam Line Break Event MSLB 21 indicates a return to power is not a significant transient analysis indicated that a small return to concern in the generation of MSLB mass and power (10 MW) could occur during an RSG MSLB energy. event initiated from no-load conditions with a stuck rod (i.e., a stuck control element assembly). This condition is not present in the OSG analysis. For completeness, the RSG MSLB M-E analysis documents additional zero power cases to allow more than a 20 MW return to power. The additional parametric cases show insignificant changes in the analysis results.

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Page 26 of 27 Response to RAI 4 RAI 4: Section 4.2.3.2.1, Page 14 of 40 - In the statement, "Although test data indicate that significant condensation of steam occurs at the safety injection location, the model accounts for only 50 percent condensation during the interval when the annulus is predicted to be full and the Safety Injection Tanks (SITs) are injecting.

No credit is taken for condensation at the safety injection location at other times,"

please explain what is the test data that indicates significantly more than 50 percent condensation occurs at the safety injection location?

Response 4: The data were compiled in test programs documented in CENPD-63 (Reference

1) and CENPD-65 (Reference 2). These programs, conducted under Atomic Energy Commission (AEC) contract AT (11-1)-2244, investigated the interaction of steam and emergency core cooling water in the intact cold leg of a PWR (CENPD-63) and the interaction of steam and emergency core cooling water in the broken cold leg of a PWR (CENPD-65). The test program, objectives, apparatus and data are described in detail in References 1 and 2.

References for Response 4:

1. CENPD-63, Rev. 1, "1/5 Scale Intact Loop Post-LOCA Steam Relief Tests,"

Combustion Engineering, March, 1973.

2. AEC-COO-2244-1, CENPD-65, Rev. 1, "Steam-Water Mixing Test Program Task D: Formal Report for TaskA, 1/5 Scale Broken Loop," Combustion Engineering, March 1973.

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Page 27 of 27 Response to Request for Additional Information Dated December 8, 2008 Response to RAI 1

RAI 1

In the letter dated August 13, 2008, SCE indicated that the 35 percent depth-based tube repair criterion remains appropriate for the replacement SGs. Please confirm that the determination of the tube repair criteria was performed in accordance with Regulatory Guide 1.121,."Bases for Plugging Degraded PWR Steam Generator Tubes." In addition, please provide the tube size

'(diameter and wall thickness) and the design differential pressure across the tubes during normal operation.

Response 1:

SCE confirms that the determination of the tube repair criteria was performed in accordance with Regulatory Guide 1. 121, "Bases for Plugging Degraded PWR Steam Generator Tubes." The tubing size is 0.75 inch outside diameter and 0.0429 inch wall thickness. The design differential pressure across the tubes during normal operation is 1458 (i.e., 2250 - 792) pounds per square inch.

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