ML20138B938

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Requests That Proprietary Presentation Matl from 970328 ACRS Meeting,Be Withheld,Per 10CFR2.790
ML20138B938
Person / Time
Site: 05200003
Issue date: 04/23/1997
From: Mcintyre B
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Quay T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19355F105 List:
References
ACRS-GENERAL, AW-97-1100, NUDOCS 9704290314
Download: ML20138B938 (96)
v • d • e


Text

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Westinghouse Energy Systems Box 355 Pittsbu@ Pennsylvania 15230 0355 Electric Corporation l AW 97-1100 l

l April 23,1997 Document Control Desk U.S. Nuclear Regulatory Commission l Washington, DC 20555 l

ATTENTION: MR. T. R. QUAY APPLICATION FOR WIT 11110LDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE

SUBJECT:

PRESENTATION MATERIAL FROM MARCll 28,1997 ACRS MEETING

Dear Mr. Quay:

l The application for withholding is submitted by Westinghouse Electric Corporation (" Westinghouse")

pursuant to the provisions of paragraph (b)(1) of Section 2.790 of the Commission's regulations. It l contains commercial strategic information proprietary to Westinghouse and customarily held in l confidence.

The proprietary material for which withholding is being requested is identitled in the proprietary version of the subject report. In conformance with 10CFR Section 2.790, Affidavit AW-97-1100 accompanies this application for withholding setting forth the basis on which the identified proprietary information may be withheld from public disclosure.

Accordingly, it 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.

l l Correspondence with respect to this application for withholding or the accompanying affidavit should reference AW-97-1100 and should be addressed to the undersigned.

Very truly yours, i //[

Brian A. McIntyre, Manager Advanced Plant Safety and Licensing jml ec: Kevin Bohrer NRC OWFN - MS 12E20 i

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9704290314 970423 PDR ADOCK 05200003 O PDR mu

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1 AW-97-1100 AFFIDAVIT  !

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COM.;ONWEALTil OF PENNSYLVANIA:

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COUNTY OF ALLEGilENY:

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Before me, the undersigned authority, personally appeared Brian A, McIntyre, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that the averments of fact set forth in this l

Affidavit are true and correct to the best of his knowledge, information, and belief:

A ,

Brian A. McIntyre, Manager Advanced Plant Safety and Licensing sworn to and subscribed before me th.is ,9ff) day Of /hI i 'I

"/( NotarialSeal Janet A. Schwab Notary Public l l

MonroeviNe Boro, AHeghony CounN My Commission Empires May 22,2000 , 1 I

Member, Pennsylvama Assocat6cn 01 Notar  !

Notary Public

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i AW-97-1100 (1) I am Manager, Advanced Plant Safety And Licensing, in the Advanced Technology Business i Area, of the Westinghouse Electric Corporation and as such, I have been specifically delegated ,

i the function of reviewing 16 proprietary information sought to be withheld from public disclosure in connection vith nuclear power plant 1 censing and rulemaking proceedings, and j am authorized to apply 'or its withholding on behallof the Westinghouse Energy Systems Ilusiness Unit.  ;

i (2) I am making this Affidavit in conformance with the provisions of 10CFR Section 2.790 of the i i

Commission's regulations and in conjunction with the Westinghouse application for withholding accompanying this Affidavit.

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(3) I have personal knowledge of the criteria and procedures utilized by the Westinghouse Energy Systems Ilusiness Unit in designating infc rmation as a trade secret, privileged or as l l

confidential commercial or financial ir. formation.

l (4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining I

whether the information sought to be withheld from public disclosure should be withheld.

i (i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.

(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, l

utilizes 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 i l l 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:

s 11694

AW-97-1100

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4 (a) The infmmation reveals the distinguishing aspects of a process (or component,

structure, tool, method, etc.) where prevention of its use by any of I Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.

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, (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 optimization or improved marketability.

l (c) Its use by a competitor would reduce 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 capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.

1 1

(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.

(f) It contains patentable ideas, for which patent protection may be desirable. I 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 the 'Vestinghouse ability to sell products and services involving the use of the information.

3 to9 A

m . _ _ _ .. _ __ _ . __

AW-97-1100

- l (c) Use by our competitor would put Westinghouse at a competitive disadvantage  ;

1 l by reducing his expenditure of resources at our expense. l i

1 (d) Each component of proprietary information pertinent to a particular i 1 l competitive advantage is potentially as valuable as the total competitive

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advantage. If competitors acquire components of proprietary information, any l

one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.

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(e) Unrestricted disclosure would jeopardize the position of prominence of 1

Westinghouse in the world market, and thereby give a market advantage to the j competition of those countries.  ;

l (f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a  ;

competitive advantage.

(iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10CFR Section 2.790, it is to be received in confidence by the Commission.

(iv) The information sought to be protected is not available in public sources or available i

1 j information has not been previously employed in the same original manner or method l l to the best of our knowledge and belief. ,

I (v) Enclosed is Letter NSD-NRC-97-5082, April 23,1997 being transmitted by I Westinghouse Electric Corporation (W) letter and Application for Withholding )

Proprietary Information from Public Disclosure, Brian A. McIntyre (W), to ,

1 Mr. T. R. Quay, Office of NRR. The proprietary information as submitted for use by Westinghouse Electric Corporation is in response to questions concerning the AP600

! plant and the associated design certification application and is expected to be applicable in other licensee submittals in response to certain NRC requirements for justification of licensing advanced nuclear power plant designs.

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l AW-97-1100

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l This information is part of that which will enable Westinghouse to:

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' l (a) Demonstrate the design and safety of the AP600 Passive Safety Systems. i

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(b) Establish applicable verification testing methods.

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. (c) Design Advanced Nuclear Power Plants that meet NRC requirements.

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(d) Establish technical and licensing approaches for the AP600 that will ultimately result in a certified design.

(e) Assist customers in obtaining NRC approval for future plants.

l Further this information has substantial commercial value as follows:

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(a) Westinghouse plans to sell the use of similar information to its customers for purposes of nweting NRC requirements for advanced plant licenses.

(b) Westing sse can sell support and defense of the technology to its customers in the licensing process.

Public disclosure of this proprietary 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 information to meet NRC l requirements for licensing documentation without purchasing the right to use the l information. i l

i 316 %

  • AW-97-1100 The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a censiderable sum of money.

In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower efTort, having the requisite talent and experience, would have to be expended for deseloping analytical methods and receiving NRC approval for those methods.

Further the deponent sayeth not.

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Enclosure 2 to Westinghouse Letter NSD-NRC-97-5082 April 23,1997 l

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i PRESENTATION TO UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS  :

l AP600 LONG TERM COOLING .

DR. L. E. HOCHREITER SYSTEMS ANALYSIS ENGINEERING WESTINGHOUSE ELECTRIC CORPORATION (412) 374-5158 f

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AP600 LONG TERM COOLING "!!!

ACRS MEETING FRIDAY, MARCH 28,1997 LONG TERM COOLING '

1. Introduction i
a. Computer Code Selection Window Mode Approach Definition b.
2. PIRT
3. WC/T Validation ,
a. OSU Model
b. Sensitivity Calculations Comparisons with Data t

c.

4. AP600 Plant Model
a. Plant Model
b. Containment Boundary Conditions
5. Conclusions 2

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t p=ij AP600 LONG TERM COOLING -

. INTRODUCTION AP6OO LONG TERM COOLING FEATURES: t

. QUASI-STEADY GRAVITY INJECTION FOR LONG PERIODS i (INDEFINITELY UNTIL THE PLANT IS RECOVERED)

. TWO INJECTION PHASES:

INITIAL INJECTION FROM IRWST WITH (HIGHER HEAD AND HIGHER FLOWS WHEN DECAY POWER IS HIGH RECIRCULATION INJECTION FROM SUMP WITH LOWER FLOWS WHEN DECAY POWER HAS DECREASED ,

REACTOR CAVITY BECOMES FLOODED, COVERS HOT AND COLD LEGS 3

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AP600 LONG TERM COOLING g AP600 Small Break LOCA and LTC Scenario

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. INTRODUCTION - CON'T ,

LONG TERM COOLING IS COMMON END POINT FOR ANY TRANSIENT WHICH ACTIVATES ADS 1-3, OR THE RCS IS DEPRESSURIZED (SBLOCA, LBLOCA).

OBJECTIVES OF THE AP600 PLANT. ANALYSIS IS TO VERIFY THAT AP600 PASSIVE SAFETY SYSTEMS .

. MAINTAIN CORE COOLABILITY INDEFINITELY

. HAVE THE SAME PEDIGREE AS SIMILAR LONG TERM COOLING SYSTEMS ON CURRENT OPERATING PLANTS.

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i AP600 LONG TERM COOLING E

. LONG TERM ANALYSIS METHOD WCOBRA/ TRAC WAS SELECTED FOR AP600 LONG TERM COOLING ANALYSIS

. ACCURATE LOW PRESSURE CALCULATIONS ARE NEEDED

. APPENDIX K TYPE CALCULATIONS WERE AGREED UPON WITH THE NRC

. IT WAS DESIRABLE TO USE AN ANALYSIS METHOD WITH WHICH THE NRC WAS FAMILIAR ,

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I I AP600 LONG TERM COOLING

. LONG TERM COOLING ANALYSIS METHOD - CON'T SINCE THE LONG TERM COOLING TRANSIENTS ARE LONG QUASI-STEADY FLOW SITUATIONS, A " WINDOW MODE" ANALYSIS METHOD HAS BEEN ADOPTED

. THE " WINDOWS" REPRESENT SELECTED TIME PERIODS FROM THE FULL TRANSIENT WHICH EXAMINE THE MOST CHALLENGING LTC CONDITIONS

. " WINDOW " CALCULATIONS ARE TYPICALLY 1000 - 2000 SECONDS IN j LENGTH FOR THE PLANT 15

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WESTINGHOUSE WCOBRA/ TRAC ,

DOCUMENTATION ,

WC/T OPERATING PLANTS

- BAJOREK, S. M., " WESTINGHOUSE CODE QUALIFICATION DOCUMENT FOR BEST ESTIMATE ,

LOCA ANALYSIS", WCAP-12945-P, JUNE 1993.

- JONES, R.C., " ACCEPTANCE FOR REFERENCING OF THE TOPICAL REPORT WCAP-12945-P, WESTINGHOUSE CODE QUALIFICATION DOCUMENT FOR BEST ESTIMATE LOCA ANALYSIS", t TAC NO. M83964, JUNE 1996.

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WC/T LONG TERM COOLING I

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- GARNER, D. C., et.al. "WC/T OSU LONG-TERM COOLING VALIDATION REPORT", WCAP-14776, NOVEMBER 1996.

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- GARNER, D. C., "WC/T VALIDATION OF AP600 LONG TERM COOLING", NDS/NRC-97-5014, t MARCH,1997.

- GARNER, D. C., et.al. "LONG-TERM CORE COOLING

SUMMARY

REPORT", WCAP-14857, '

MARCH,1996.

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WESTINGHOUSE WCOBRA/ TRAC DOCUMENTATION h

  • SER REQUIREMENTS FOR APPROVED VERSION OF WCAP-12945-P:

- ROADMAP UP FRONT

- RE-WRITTEN TO REFLECT FINAL METHODOLOGY

- WELL INDEXED, WITH RELEVANT RAIS REFERENCED WITHIN THE REPORT

= W HAS RE-SCHEDULED THE COMPLETION DATE TO 5/30/97 (NSD-NRC-97-5011)

  • MAGNITUDE OF THE TASK:

- ORIGINAL DOCUMENT HAD 28 SECTIONS, TOTALLING - 5,000 PAGES

- RAI RESPONSES, METHODOLOGY REVISIONS, ETC. TOTALLED ANOTHER

- 10,000 PAGES

  • STATUS:

- 20 OF 28 SECTIONS REWRITTEN

- 7 TO 8 MAN-MONTHS INVESTED 17 I

AP600 LONG TERM COOLING .q

- DURING THE LTC TRANSIENT, THE PLANT PRIMARY SYSTEM IS IN A ONCE THROUGH COOLING MODE WITH INJECTION INTO THE DVI LINE AND VENTING OUT THE ADS STAGE 4 VALVES

. THE REACTOR SYSTEM TRANSIT TIME IS APPROXIMATELY 300 - 700 SECONDS DEPENDING ON THE TIME PERIOD

. SINCE THE WINDOW MODE CALCULATIONS ARE FOR LONGER TIME PERIODS, THE RESULTING QUASI-STEADY STATE FOR THE REACTOR SYSTEM IS DRIVEN BY THE IMPOSED BOUNDARY CONDITIONS, NOT THE INITIAL CONDITIONS ,

. THE INITIAL CONDITIONS (SUCH AS VESSEL LEVELS OR MASS DISTRIBUTION) WILL BE SWEPT AWAY BY THE IMPOSED BOUNDARY CONDITIONS OF, DVI LINE FLOW l

CORE POWER CONTAINMENT PRESSURE 18 ,

AP600 LONG TERM COOLING p_.ylr

- AS A RESULT, A REASONABLE SET OF INITIAL CONDITIONS ARE ADEQUATE TO INITIALIZE A WINDOW MODE CALCULATION SINCE AT THE '

END OF 1000 - 2000 SECONDS. THE RESULTS REFLECT THE IMPOSED BOUNDARY CONDITIONS.

- IN THIS FASHION, THE LONG TIME PERIODS OF THE LTC TRANSIENT CAN BE DIVIDED INTO SHORTER TRANSIENTS WHICH CAPTURE THE MOST i

IMPORTANT TIME PERIODS TO SHOW ADEQUATE CORE COOLING SEVERAL DIFFERENT CALCULATIONS ARE PERFORMED TO EXAMINE

! DIFFERENT LTC SITUATIONS TO ASSURE ADEQUATE CORE COOLING 1

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AP600 LONG TERM COOLING -

i AP6OO LONG TERM COOLING PIRT 20

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ll l.!*i11 AP600 LONG TERM COOLING .

. AP600 LONG TERM COOLING PIRT LTC PIRT WAS DEVELOPED AND REVIEWED AT WESTINGHOUSE AND i

HAS BEEN SUBMITTED TO THE NRC AS PART OF THE LTC V&V REPORT (WCAP-14776)

SOME PHENOMENA WHICH WERE INITIALLY RANKED HIGHER ARE

! NOW RANKED LOWER BASED ON THE OSU TEST ANALYSIS AND OSU SIMULATIONS COMMENTS HAVE BEEN RECEIVED FROM THE NRC AND ITS CONSULTANTS, AND HAVE BEEN INCLUDED IN THE FINAL LTC PIRT.

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l l AP600 LONG TERM COOLING g j TABLE 11 l PHENOMENA IDENTIFICATION RANKING TABLE l FOR AP600 LOCA LTC TRANSIENT (Rev.1) >

Component IRWST Sump l Phenomenon Injection " Injection " l Breax Cnucal Cow M N/A Swbsonic Cow M L ADS Suges I to 3 Cnucal now M N/A Subsonic dow M L Tao-phase pressure drop L L Valve loss coefficients M/L L Steg'e phase pressure drop L L Vessel / Core f Decay heat H H Row resisance L L Flashing N/A N/A Wall-stored energy M M Natural circulauon now and heat transfer M M Mixture level mass inventory H H Pressunter Pressunzer Guid level L N/A Wall stored heat L N/A Pressunzer Surge Line Pressure droprnow regime L L Downcomer/ Lower Pienum Pressure H H Liquid level H H M M Condensauon ,

1 L'pper Head Liquid level N/A N/A l

Flow through downcomer top nozzles M M

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l AP600 LONG TERM COOLING TABLE 11 (Cont) l PHENOMENA IDENTIFICATION RANKING TABLE FOR AP600 LOCA LTC TRANSIENT (Rev.1) l i

Component IRWST Sump Phenomenon lajection " !ajecnon " l i

l'pper P'enum Liquid level H H Entrainment/dcentrainment M M  !

Cold Legs Condensauon L L Separauon at bajance line tee L L Steam Generator 20 - natural cir:ulacon N/A N/A Steam generator tea :ansfer LNA'2' N/A l Secondarv condiues LNA'2' N/A Hot Leg Flow panem transiuon H/M H/M Separauon at ADS 4 tee H/M H/M

.GS4 Cnucal dow H N/A Subsonic dow H H CMT Recirculauen injecuon N/A N/A Gravity draarung injecuon L L Vapor condensauon rate L L CMT Balance Lines P essure drop N/A N/A Flow composioon L L Accumulators Noncondensible gas entrainment N/A N/A

! IRWST Gravtry drain:ng injecuen H M Vapor condensauon rate L L Temperature distnbuuon M M 23

AP600 LONG TERM COOLING g TABLE 11 (Cont) I

)

PHENOMENA IDENTITICATION RANKING TABLE FOR AP600 LOCA LTC TRANSIENT (Rev.1)

Component IRWST Sump I l Phenomenoa Injection " !ajection " l ,

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DVI Line I

' Pressure drop H H I

1 PRHR i Liquid natural ctreulanon flow and heat transfer N/A N/A l 5urnp Gravity draining injecuen N/A H Level N/A H Temperature N/A H Note:

1. H = High M = Medium
L = Low N/A = Not Applicable 1
2. De ranungs for steam generator heat transfer and secondary condicons are Low for IRWST injecuen after 1 a large ereak and Not Applicable for IRWST injecuon after a small break.

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4 h

24

P

\M PRESENTATION '

l TO UNITED STATES NUCLEAR REGULATORY COMMISSION i ADVISORY COMMITTEE ON REACTOR SAFEGUARDS AP600 LONG TERM COOLING D.C. GARNER SYSTEMS ANALYSIS ENGINEERING WESTINGHOUSE ELECTRIC CORPORATION (412) 374-5352

l l

I l 2 l

l l WC/T Code Validation for __

AP600 Long-Term Cooling g 1

- Overview of OSU Test Data i

- Test to Test Similarities i - Significant Flow Rates l

- Vessel Pressure Variations

- Summary of Westinghouse Topical Report (WCAP-14776)

- Recent Extended Time Calculational Results (NSD/NRC-97-5014) l l

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6 OSU Measured Flow Rates at End of IRWST Draindown g Test / Time SB01/ SB10 / SB12 / SB23/

Vessel inflows 14,500 sec 14,000 sec 9,000 sec 14,500 sec DVI-1 (Ib/sec) 0.530 0.520 1.140' O.540 DVl-2 (Ib/sec) 0.520 0.540 0.300 0.560 Total Vessel Inflow (Ib/sec) ** 1.050 1.060 1.440 1.100 Vessel Outflows Break Flow (Ib/sec) -0.030 0.070 -

-0.025 ADS 1,2,3 Flow (Ib/sec) 0.006 0.003 0.011 0.014 ADS 4-1 Flow (Ib/sec) 0.530 0.710 0.450 0.960 ADS 4-2 Flow (Ib/sec) 0.550 0.580 0.550 Total Vessel Outflow (Ib/sec) ** 1.056 1.033 1.301 0.989 Broken DVI line has low hydraulic resistance

    • Inflow and outflow measurements match within the 20 flow measurement uncertainty of 0.14 lb/sec

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- In the latter half of IRWST injection and during sump injection, reactor vessel conditions are largely independent of break size and location. *

- Reactor vessel liquid levels

- DVI and ADS 4 flow rates

- Reactor vessel pressure i

- In the same time period, pressures in the downcomer, upper  !

plenum, and upper head are essentially equal. l

- As a consequence of the above, collapsed liquid levels in the downcomer and core / upper plenum are essentially equal. l

  • Only partially true of DVI line breaks due to substantially reduced resistance to vessel inlet flow.

10 ;

l WC/T Code Validation for AP600 __

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Long Term Cooling Analysis l

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Letter Rpt.

WCAP-14776 NSD/NRC-97-5014

@ WC/T Performance in WC/T Performance in Window Mode Calculations Window Mode Calculations

1. ExtendedTime Sensitivity N1. Initial Condition Sensitivity 2. Boundary Cond.

Sensitivity hj WC/T Validation Summary of WC/T WC/T LTC i Loop and Vessel M for 7 Applicability Models i AP600 Long Term for Plant Cooling Analysis Calculations Letter Rpt.

WCAP-14776 NSD/NRC-97 5014 WC/T and OSU Data WC/T and oSU Data Comparisons of Comparisons of

@ SB01,SB10.

SB12 & SB23 SB01 & SB10

1. 3000 Sec.

l Windows 1

11 1

OSU - WC/T Modeling l

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- Boundary Condition Inputs ,

- Initial Condition inputs

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"._1_4 7- , H L' ~ ~ ' 7 17 - ~ ~ 76~ ~ ~ ~ ~ ~ ~ ~ ~ ~ T ' 3 ~' ,$

T  :

I a

T i._T 'iT

_ 'iT_

'IT

, "f51

- i _I ' _iT_

O I 3 , 12 v I

. s s s s s s s s s s s.

e 4 i i 23 i

f 2 4 6 7=

T_ S_ iT 1 t

. 17 l

t I f t

4 13 d i T._. 11 1 ]I T -

e p

OSU - WC/T Long-Term Cooling m i

Boundary Conditions No. Condition / sbO1 sb10 sb12 sb23 Source of data Calc initiation Time (sec) 14,000 13,500 8500 14,000

1. IRWST Level (Rel. to drain) (in) 19.5 20.5 19.5 27.5 CLDP-701
2. IRWST Temperature ( F) 95 94 90 130 TF-713
3. Sump Level (Rel. to drain) (in) 59 57 64 58 CLDP-901
4. Sump Temperature ( F) 165 177 87 172 TF-904, 909
5. Break Separator Level (in) 105 102.5 103 110 CLDP-905
6. Break Separator Temp (*F) 150 152 187 182 TF-908
7. Core Makeup Tank 1 Flow (Ib/sec) 0 0 0 0 CLDP-507
8. Core Makeup Tank 1 Temp ( F) 132 69 200 148 TF-501
9. Core Makeup Tank 2 Flow (Ib/sec) 0.3/0.1 0 0 0 CLDP-502
10. Core Makeup Tank 2 Temp ( F) 114 162 190 153 TF-504
11. SG Secondary Side Temp ( F) 290 295 322 290 TF-305, 307, 306, 308
12. SG Secondary Side Press (psia) 58 62 92 58 TF-305, 307, 306, 308 Core Power Factor 0.243 0.244 0.283 0.243 KW-102,103 13.

OSU - WC/T Long-Term Cooling - - -

i Initial Conditions No. Condition / sbO1 sb10 sb12 sb23 Source of data Time of Start of IRWST (sec) 1262 810 360 2980 56 56 56 56 CLDP-116,140

1. Upper Plenum Level (in)
  • 56 56 56 56 CLDP-116,140
2. Downcomer Level (in)
  • Downcomer Fluid Temp. ( F) 190 150 190 200 TF-155,156,130,131 3.

Vessel Wall Metal Temp. ( F) 200 150 190 200 TF-155,156,130,131 4.

5. Core Liquid Terap. (F) 212 212 212 212 WCAP-14252 Initial Fuel Rod Temp. ( F) 212 212 212 212 TH-307, 309,102,103 6.
7. Hot Leg Level (in) Empty Empty Empty Empty CLDP-207,208
8. SG Channel Head Level (in) Empty Empty Empty Empty CLDP-209,214
9. Cold Leg Level (in) Empty Empty Empty Empty CLDP-116,140
10. Pressurizer Level (in) Empty Empty Empty Empty CLDP-601
11. Surge Line Level (in) Empty Empty Empty Empty CLDP-602
  • Relative to the bottom of the vessel

16 WC/T Validation Calculations for Long-Term Cooling Analysis g

1. WC/T Initial Condition Sensitivity - WCAP-14776

- Fixed boundary conditions

- Varied individually vessel initial conditions

- Vessel liquid level

- Downcomer temperature

- Tests SB01 and SB10

2. WC/T Extended Time Calculation - NSD/NRC-97-5014

- Reference calc., SB01,1260 sec. to 4600 sec.

- Comparison calc., SB01,3600 sec. to 4600 sec.

- Identical vessel initial conditions

- Appropriate, time dependent boundary conditions

3. WC/T Boundary Condition Sensitivity - NSD/NRC-97-5014

- Reference calc., SB01,8000 sec. to 9000 sec.

- Comparison calc., SB01,8000 sec. to 9000 sec.  !

- IRWST level raised 2.5 ft for 200 sec. (3600 sec level)

- Core Power raised 30% for 200 sec. (3600 sec value)

- S.G. Temp. raised 45 F for 200 sec. (3600 sec value)

- Identical vessel initial conditions (8000 sec. value)  ;

1

4. WCA" Comparison with OSU Test Data

- WCAP-14776

- SB01,2' CL Break,14,000 sec. to 15,000 sec.

- SB10, CMT Balance Line Brk.,13,500 sec. to 14,500 sec. l l

- SB12, DEG DVI Line Brk., 8,500 sec. to 9,500 sec.

SB23,1/2' CL Break,14,000 sec. to 15,000 sec.

- NSDINRC-97-5014

- SB01, 2' CL Break,1,260 sec. to 4,600 sec.

- SB01,2' CL Break, 8,000 sec. to 9,000 sec.

l - SB10, CMT Balance Line Brk.,13,500 sec. to 16,500 sec.

i 17 l

l WC/T Code Validation for AP600 --

l Long Term Cooling Analysis l

l Letter Rpt.

WCAP-14776 NSD/NRC-97-5014 WC/T Performance in WCfr Performance in Window Mode Calculations

1. Initial Condition Sensitivity Window Mode Calculations
1. ExtendedTime Sensitivity
2. Boundary Cond.

Sensitivity l

O WC/T

@ Summary

' WC/T LTC '

Validation of WC,T .

Loop and Vessel M for 7 Applicability Models i AP600 Long Term for Plant Cooling Analysis Calculations Letter Rpt.

WCAP-14776 NSDiNRC-97-5014 WC/T and OSU Data WC/T and OSU Data Comparisons of Comparisons of

@ SB01,SB10, SB12 & SB23 SB018. SB10

1. 3000 Sec.

@ I Windows

18 Sensitivity to Initial Conditions - SB10 g Initial Vessel Liqui.d Level Sensitivity

- Upper Plenum Collapsed Liquid Level Downcomer Collapsed Liquid Level DVI-1 Injection Flow ADS 4-1 Flow Initial Downcomer Liquid Temperature Sensitivity

- Upper Plenum Collapsed Liquid Level Downcomer Collapsed Liquid Level i DVl-1 Injection Flow ADS 4-1 Flow l

19 i OSU Collapsed Liquid Level i

Reference Elevations l

Elevations h

i l Hot Leg Centerline - 67.1" (14.4" wrt UCP) i Cold Leg Centerline - 71.5"

DVI Line Centerline - 62.1" Top of Downcomer - 87.1"

} Top of Core - 13.1" + 39.6" = 52.7" l

Top of Upper Plenum - 52.7" + 20.6" = 73.3" i

l -

i l f L~-

_ _ _ g,,, - - -

- Upper Plenum Reference Level - 52.7 inches 1

i 11l - Core Reference Level - 13.1 inches i

gk -

Downcomer Reference Level - 0.0 inches i

1

The Following Figures are in the Proprietary Version of this Presentation Figure 3-22 Figure 3-20 1 Figure 3-25 Figure 3-31 Figure 3-38 Figure 3-36 I

Figure 3-41  !

i Figure 3-47

28 WC/T Code Validation for AP600 Long Term Cooling Analysis Letter Rpt.

WCAP-14776 NSD/NRC-97 5014 WC/T Performance in WC/T Performance in

@ Window Mode Calculations Window Mode Calculations i

I

1. Initial Condition Sensitivity 1. ExtendedTime Sensitivity
2. Boundary Cond.

Sensitivity G WC/T

@ Summary WC/T LTC t Validation of WCfr Loop and Vessel  % for .

[ Applicability Mooels L AP600 Long Term for Plant Cooling Analysis Calculations Letter Rpt.

WCAP-14776 NSD/NRC-97-5014 WC/T and OSU Data WC/T and OSU Data Comparisons of Comparisons of

@ SB01, SB10 SB01 & SB10 @

SB12 & SB23 1. 3000 Sec.

Windows

29 1

l l

WC/T Extended Time Sensitivity - SB01 g Schematic Description of Calculations l

W Start of IRWST Draindown T

I O i

.9 l '

E '

D I '

! 3 l t

y #

j $ _. __ __ _ __ __

__d-__

g Identical Initial Vessel Conditions  !

C l f s

1260 3600 4600 4

Tirne (sec) 9 5'

i s

30 WC/T Extended Time Sensitivity - SB01 g

- Upper Plenum Collapsed Liquid Level Downcomer Collapsed Liquid Level -

Core Collapsed Liquid Level DVI-1 injection Flow -

Integrated DVI-1 Flow ADS 4-1 Flow Integrated ADS 4-1 Flow

The Following Figures are in the Proprietary Version of this Presentation Figure 2.1-4 Figure 2.1-2 Figure 2.1-3 Figure 2.1-7 Figure 2.1-8 Figure 2.1-13 Figure 2.1-14

1 38 ;

i I

\

l WC/T Boundary Condition Sensitivity - SB01 IB l l

I Schematic Description of Calculations i l

l a

E Ref. Secondary Temp. + 45'F y

& 'T

[

~8 w ,

O l c

w -

Ref. Decay Heat + 30%

&s "

E e l

'N ,

t 8 O 8 ' l I

- Ref. Level + 2.5' j

3 'm l Ys o x_

8200 8300 9000 8000 I Time (sec) i t

i

39 WC/T Boundary Condition Sensitivity - SB01 g

- Upper Plenum Collapsed Liquid Level

- Downcomer Collapsed Liquid Level Core Collapsed Liquid Level DVI-1 Injection Flow Integrated DVI-1 Flow ADS 4-1 Flow Integrated ADS 4-1 Flow l

1 - - _ - - _ - _ - _ _ _ _ _ .-____.-_ ___ _ ____

The Following Figures are in the Proprietary Version of this Presentation Figure 2.2-4 Figure 2.2-2 Figure 2.2-3 Figure 2.2-7 Figure 2.2-8 Figure 2.2-13 Figure 2.2-14 f

47 WCTF Code Validation for AP600 Long Term Cooling Analysis g 8

Letter Apt.

WCAP 14776 NSD/NRC-97 5014

@ WC/T Performance in WC/T Performance in Window Mode Calculations Window Mode Calculations @

1. Initial Condition Sensitivity 1. ExtendedTime Sensitivity
2. Boundary Cond.

Sensitivity G W C/T Summary 1 WC/T LTC M[ Validation of WC/T l

Loop and Vessel for 7 Applicability l Models s AP600 Long Term for Plant Cooling Analysis Csiculations Letter Rpt.

WCAP-14776 NSD/NRC-97-5014 WCfT and OSU Data WC/T and OSU Data Comparisons of Comparisons of SB01, SB10, SB12 & SB23 SB01 & SB10

1. 3000 Sec.

Windows

I 48 i Test Data Comparisons - SB01 g Upper Plenum Collapsed Liquid Level Downcomer Collapsed Liquid Level Total DVI-1 Injection Flow l

ADS 4-1 Flow ,

l l

l l

l l

l l

l l

l l

3 The Following Figures are in the Proprietary Version of this Presentation Figure 5.1-23 Figure 5.1-24 Figure 5.1-7 Figure 5.1-17 I

P 6

53 WCTT Code Validation for AP600 Long Term Cooling Analysis g Letter Rpt.

WCAP-14776 NSD/NRC-97-5014

@ WC/T Performance in Window Mode Calculations WC/T Performance in Window Mode Calculations @

1. Initial Condition Sensitivity 1. ExtendedTime Sensitivity
2. Boundary Cond.

Sensitivity Q WCTF Summary

' WC/T LTC i Validation of WC/T Loop and Vessel 5 for 7 Applicability Models i AP600 Long Term for Plant Cooling Analysis Calculations l

Letter Rpt.

WCAP-14776 NSD/NRC-97 5014 WC/T and oSU Data WC/T and oSU Data Comparisons of Comparisons of

@ SB01.SB10.

SB12 & SB23 SB01 & SB10

1. 3000 Sec.

Windows

1 54 l WC/T Extended Time Calculation - - . - - - -

SB01 from 1260 sec. to 4600 sec. g l

l

- Upper Plenum Collapsed Liquid Level Downcomer Collapsed Liquid Level  !

l Core Collapsed Liquid Level DVI-1 Injection Flow Integrated DVI-1 Flow ADS 4-1 Flow Integrated ADS 4-1 Flow l

The Following Figures are in the Proprietary Version of this Presentation Figure 2.3-23 Figure 2.3-24 Figure 2.3-22 Figure 2.3-7 Figure 2.3-8 Figure 2.3-17 Figure 2.3-18 1

l 1

4

i 62 l l

1 l

WC/T Extended Time Calculation -

SB01 from 8000 sec. to 11000 sec. g

- Upper Plenum Collapsed Liquid Level Downcomer Collapsed Liquid Level Core Collapsed Liquid Level DVl-1 Injection Flow Integrated DVI-1 Flow ADS 4-1 Flow Integrated ADS 4-1 Flow i

l l

The Following Figures are in the Proprietary Version of this Presentation Figure 2.4-23 Figure 2.4-24 Figure 2.4-22 Figure 2.4-3 Figure 2.4-8 Figure 2.4-17 Figure 2.4-18

70 WC/T Extended Time Calculation - . . .

I SB10 from 13,500 sec. to 16,500 sec. g l

l

- Upper Plenum Collapsed Liquid Level Downcomer Collapsed Liquid Level Core Collapsed Liquid Level ,

l DVI-1 Vessel inlet Temperature IRWST DVI-2 Injection Flow Sump Injection 2 Flow l

Total DVl-2 Injection Flow Total Integrated DVI-2 Flow Total ADS 4 Flow Total Integrated ADS 4 Flow l

l l

t l

i

(

l The Following Figures are in the Proprietary Version of this Presentation i

Figure 2.5-23 Figure 2.5-24 1

i Figure 2.5-22 Figure 2.5-11 Figure 2.5-4 t

Figure 2.5-6 Figure 2.5-9 t

Figure 2.5-10 Figure 2.5-19 i

Figure 2.5-20 I

i t

81 l

l WC/T Code Validation for AP600 l Long Term Cooling Analysis l I

l J

l Letter Rpt.

WCAP 14776 NSD/NRC-97 5014 x

@ WC/T Performance in WCfr Performance in N Window Mode Calculations

1. Initial Condition Sensitivity Window Mode Calculations
1. ExtendedTime Sensitivity
2. Boundary Cond.

Sensitivity

@ WC/T @ Summary WC/T LTC r Validation of WC/T Loop and Vessel Models M'

for AP600 Long Term 7 Applicability for Plant Cooling Analysis Calculations Letter Rpt.

WCAP-14776 NSD/NRC-97-5014 WC/T and OSU Data WCfT and OSU Data Comparisons of Comparisons of

@ SB01, SB10, SB12 & SB23 SB01 & SB10

1. 3000 Sec.

Windows O

. 1 1 1 82 1 1

Summary of WC/T vs. OSU Data g l

- Upper Plenum Level Comparison i - Downcomer Level Comparison

- Total Vessel Inflow (DVI) Comparison l

l - Total Vessel Outflow Comparison l

- WC/T Total inflow / Outflow Comparison

- Vessel Pressure Comparison 1

l l

83 1

g Upper Plenum Liquid Level Comparison i

\

l _ 25 l l

l C - l

. l v I 2c Sensor Uncertainty ~+ i e r l

> 20 o /

a E

~3 I

+-

i C

a

, n

- 15 b -

a I i c.

9 c.

3 10 I

a l i

a r #

o 9

3 5.

e **

o L U i r Conservative Direction I L

N i y L 3: n 0 5 1'O 15 2'O 25 l CSU Meosured Upper Plenum LeveI (in) 1 I

l

84 Downcomer Liquid Level Comparison 1

1

_ 75 f' c

/ i

- 2c Sensor Uncertainty -- +

70 1

o -

j

~

i

- i

('

o C

E 65  :

u _

e 5 .

b  !,

c i a [

r 60 o I

- I ,

c L I

I O

=

u

- c5 c

u ((

L

- i Conservative Direction {

s t.

u F

  1. 50 . .

55 60 65 70 75 50 OSU Measured Downcomer LeveI ( n)

85 Reactor Vessel Total Inflow Comparison gj l

- 2 u -

{

e l

{.o r 2a Sensor Uncertainty -*- ,$, l

- / ,

~2 , ~s

\

~

, d ./

/ .

2 F ././ l

/

- 1 o .-  ;

[ r ,

, ' la /,

> I y v.  ! i

, . / /1 '

u r Mean of Calculations i I

- i I

O -

c l

1 3 I U

l O

" 5

_ i o  !

t c -

~ l

,_ t s L o

5 0 0 5 1 15 2 OSU Total Measured VesseI infIow (Ib/sec)

86 Reactor Vessel Total Outflow Comparison lg l

l - 2 ,

l v ,

O M

s

.o 2c Sensor Uncertainty + ' ^ /

l  ;

/ \

Z,

, / l l

~

~

. // .

l  ;

I

. .f/' i

. 7,  !

m r -

l l ~ , l / ,/ ,

./M;  !

I l Mean of Calculations

  • l e

= L l v e

u 5-r e

l C

t l s .

l u 3" 6 0 .5 1 15 2 OSU ictal Measured Vessel Outflow (Ib/sec) 4 6

l l -

^

l l

l I

l 87 l l

1 1

WC/T Total Inflow / Total Outflow Comparison g l v

a 2[- -

[ i l

sn x

a ,

1 l

l .  !

o

_ 1 .3

/ \

~ /t ,

o /  ;

i O

i

=

l e -

v

> t e

o

" i V

e

  • u 5 -

t e i o I

- I.

l F

~

s l-o  !

  • 0 . .

0 5 1 15 2 WC/T Total Calculated Vessei Infiow (lb/sec) l l

l

1 1

l l I 1 1

1 i

I I

1 I

.C.

w 3

w l l l G  ;

(

i I

u 1 n.Ed b

i

  • C w

fume C

C

.C.

~

u i

b i G w

Wust

.U.

C= 6 i

C C b M l m ~

t m

o Aw

.N -

6 3

i

, u b i l

l C i

.cc u l C

=

l C

M C ,

IZn i O

.O l h i

i I

I a

1 89 Vessel Pressure Data Comparison i l _

! l l

l 1 l

l l l - Measured vessel (upper head) pressure range is 15.5 psia to 16.0 psia with l a pressure sensor uncertainity of 2.44 psia at the 2c uncertainty level.

- Calculate pressure of all tests were in the range of 15.3 psia to 15.9 psia l during IRWST draindown and sump operation.

l

- Calculated vessel pressures show a favorable comparison with the measured values, i.e. well within the uncertainty bands.

l

1 l

1 90 !

Conclusions from WC/T Code Validation for AP600 Application g i

1. WC/T calculations show no solution divergence at 1000 seconds and no solution divergence for extended time calculations of 3000 seconds or approximately 5 to 10 times the period required to reach a quasi-equlibrium solution.

- Extended Time Sensitivity Solution

- Boundary Condition Sensitivity Solution

- 3 Data Comparison Solutions

2. WCTT underpredicts reactor vessel collapsed liquid levels slightly in OSU tests which provides a degree of conservatism.
3. WC/T predicts total vessel inflows and outflows in the OSU tests within the 2a uncertainty of the flow sensors.
4. WC/T predicts the reactor vessel pressures in the OSU tests within the 2a uncertainty of the pressure sensors.

h i

i PRESENTATION TO UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS t

AP600 LONG TERM COOLING R.M.KEMPER SYSTEMS ANALYSIS ENGINEERING WESTINGHOUSE ELECTRIC CORPORATION

, (412) 374-4579 i

j

AP600 LONG TERM COOLING SSAR CALCULATIONS L U" WITH WCOBRA/ TRAC AP600 LONG TERM COOLING FEATURES PASSIVE SAFETY-RELATED SYSTEMS QUASI-STEADY-STATE CONDITIONS OSU V&V ESTABLISHED THE WCOBRATTRAC LTC NODALIZATION

  • CALCULATE AP600 PERFORMANCE AT LIMITING, DISCRETE TIMES ,

USING WINDOW MODES

/cm/451rmk wpf P.sge 1

METHODOLOGY TO PERFORM A WINDOW MODE lll l ECCS PERFORMANCE ANALYSIS

~

1. IDENTIFY LIMITING PORTIONS OF THE LTC PHASE, THE MOST DEMANDING ON THE SAFETY SYSTEMS.
2. ESTABLISH BOUNDARY CONDITIONS FOR WCOBRA/ TRAC.

3.- SELECT REPRESENTATIVE INITIAL CONDITIONS FOR CALCULATION.

4. EXECUTE WCOBRA/ TRAC UNTIL QUASI-STEADY STATE ACHIEVED.

Icm/451rmk wpt Pages 2

i q"

SSAR LONG TERM COOLING ANALYSIS STRATEGY

. USE WCOBRATTRAC, SHOWN CAPABLE OF REALISTIC / CONSERVATIVE LTC ANALYSES BY V&V USE APPENDIX K REQUIRED FEATURES (102% INITIAL POWER; 1971 ANS DECAY HEAT + 20%)

APPLY ADDITIONAL CONSERVATISMS IN DEFINING PLANT '

CONDITIONS.

FOR INSTANCE, FOR WINDOWS AT START OF SUMP RECIRCULATION, APPLY A HIGH IRWST DRAIN RATE DURING IRWST INJECTION:

TO MAXIMlZE DECAY HEAT AT SUMP INITIATION TO MAXIMlZE ENERGY CONTENT OF LIQUID EXITING ADS-4 DURING IRWST INJECTION TO MAXIMlZE SUMP TEMPERATURE RELATIVE TO CONTAINMENT PRESSURE ADDRESS A SPECTRUM OF LOCA BREAK SIZES SMALL RCS LOOP BREAK DEDVIBREAK DECLG BREAK

/criv451rmk wpf Page 3 i

WGOTHIC COMPUTES CONTAINMENT CONDITIONS  !"!

THROUGHOUT THE TRANSIENT

- NO GUTTER RETURN OF CONDENSATE TO IRWST

  • CONSERVATIVE ASSUMPTIONS APPLIED MASS / ENERGY RELEASES MAXIMUM PCS WATER FLOW EXTERNAL TO CONTAINMENT MINIMUM PCS WATER TEMPERATURE 1.05* BEST ESTIMATE FREE VOLUME NO MODELING PENALTIES THAT MINIMlZE HEAT TRANSFER f

MINIMlZE INITIAL AIR MASS PRESENT

- THESE RESULT IN A LOW CONTAINMENT PRESSURE AND A HIGH SUMP TEMPERATURE l

/cm/451rmk wpf Page 4

. . . . . . , . - . - . - + -

l j Small Break LOCA Window Mode LTC Calculation l NOTRUMP Short 1

Term Analysis I

l U 1

' ss & Energy Mass & Energy ele ses Dudng Data IRWST Drain l 1

l i

V U

l. Containment Pressure

= 2. Sump Levels WGOTHIC (Time Zero into Sump 3. Sump Temperatures Injection)

U Select Window Mode Times and l Boundary Conditions Case 1 Case 2 Case N u u u WC/T WC/T WC/T LTC LTC LTC Cale Calc Calc o o o Chapter 15.6 SSAR (RCS & Core Conditions) l c msworssitccaic pre 03 897 ses G

f  !!

INITIAL CONDITIONS FOR WINDOW CALCULATION

  • INITIAL CONDITIONS ARE ESTIMATED AND DO NOT DETERMINE THE QUASI-STEADY STATE OBTAINED PRIMARY CIRCUIT LIQUID LEVELS AND TEMPERATURE STRUCTURE TEMPERATURES

- WINDOW APPROACH HAS SHOWN THAT AN EQUIVALENT QUASI-STEADY STATE WILL BE REACHED FROM ANY REASONABLE VALUES FOR THESE INITIAL CONDITIONS, AS VALIDATED BY OSU SIMULATIONS

  • ANALYZE AP600 CASES USING INITIAL CONDITIONS ESTIMATED FROM EARLIER CALCULATIONS

/uTV451rmk wpt Pageb

1 BOUNDARY CONDITIONS FOR WINDOW CALCULATION BOUNDARY CONDITIONS WHICH DETERMINE THE QUASI-STEADY STATE CORE POWER (APPENDIX K DECAY HEAT)

IRWST LIQUID LEVEL AND TEMPERATURE CONTAINMENT PRESSURE SUMP LIQUID LEVEL AND TEMPERATURE

/cm'451rmk wpf Page 7

i'n" '

CRITERIA FOR ACHIEVING A QUASI-STEADY STATE '

  • KEY VARIABLES REMAIN STEADY OVER AN EXTENDED PERIOD CORE LIQUID LEVEL DOWNCOMER LIQUID LEVEL UPPER PLENUM LIQUID LEVEL UPPER PLENUM PRESSURE DVI INJECTION RATE .

ADS STAGE 4 FLOW

/ crib 451rmk wpf Page8

lll"  !

AP600 LONG-TERM COOLING CASES FOR FINAL SSAR  :

CONSERVATIVE ANALYSIS BASES UTILIZED CONTAINMENT CONDITIONS SINGLE FAILURE OF ONE PASSIVE SAFETY SYSTEM  !

COMPONENT APPENDIX K DECAY HEAT i

MAXIMUM DESIGN FLOW RESISTANCES FOR INJECTION PATHS AND ADS PATHS MODELING PER THE WC/T OSU FINAL VALIDATION REPORT CASES TO SHOW ADEQUATE CORE COOLING IN THE LONG TERM l

!cnv451rmk wpf Page 9

+

AP600 Injection Flow Sequence -

Small Break LOCA

~

h

_ ii

'! Accumulator

!:I y i

i i Peak Flows l

i Y;g ,

hl' .I CMT f- [' f lRWST ,

l WC/T Window A i l ll 3I \

l' , ,, Sump i

ll ll ll

,' II i

II ll

~ ,,

ll i.

- -/ _t \\ \\

igg i i \\ l i i i 5000 10,000 15,000 20,000 35,000 40,000 50,000 400,000 Approximate Time (sec) t li)

l "!i!

AP600 SSAR LONG-TERM COOLING WINDOW MODE ANALYSES 'i CASE 1 - DOUBLE-ENDED DVI LINE BREAKS SET I - DESIGN BASIS: ONLY PASSIVE SYSTEMS OPERATE WINDOWS INCLUDE THE LATE IRWST INJECTION PHASE AND THE '

INITIATION OF STABLE SUMP INJECTION REPRESENTS EARLIEST SWITCHOVER TO SUMP RECIRCULATION AND, THEREFORE, THE HIGHEST DECAY POWER FOR SUMP INJECTION SET 11 - SYSTEMS INTERACTION: RNS OPERATION INITIALLY AFTER IRWST HAS BEEN DISCHARGED RAPIDLY BY PUMPS, RNS FAILURE ASSUMED AT THE TIME OF SUMP SWITCHOVER .

SUMP INJECTION BEGINS EARLIER THAN IT DOES IN SET I: SAME WINDOWS AS IN CASE 1, SET I SET lil - WALL-TO-WALL FLOOD UP IN THE VERY LONG-TERM WINDOW MODELS THE LEVEL REACHED WHEN ALL COMPARTMENTS BELOW LIQUID SURFACE HAVE FILLED DUE TO ~

PASSIVE LEAKAGE MINIMUM SUMP LEVEL FOR DESIGN BASIS EVENTS

/cnV451rmA wpf Pagte 11

e n.

AP600 SSAR LONG-TERM COOLING WINDOW MODE ANALYSES CASE 2 - SMALL COLD LEG BREAKS SET I - TWO-INCH COLD LEG BREAK WITH ONE ADS-4-PATH FAILED t

WINDOWS INCLUDE THE LATE IRWST INJECTION PHASE AND THE INITIATION OF STABLE SUMP INJECTION REPRESENTATIVE OF SMALL BREAK LOCA SWITCHOVER TO INJECT FROM A NEAR-SATURATED SUMP i i

SET 11 - TWO-INCH COLD LEG BREAK WITH ONE DVI PATH FAILED SAME WINDOWS AS IN CASE 2, SET I SINGLE FAILURE SENSITIVITY CASE

/criv451rmk wpf Page 12

F wcrr "l AP600 Injection Flow Sequence -

i Extended > Large Break LOCA '

l Analysis l l l I

' ;! I ll l l Accumulator WC/T Window

~

l e i i l i ii ll s

I Peak Flow ll ii i e i ii

~

'l

( 'CMT ll g ' I IRWST

, / Vll e~ 1! '/

5 _

il O

l Il all i

ll  !

] Sump ll

~

, i ,

i I

i ll ii

, [  !

l i i

~

il 1 > l

'l o k -

r i

\\ \\

i i

\\ l l 1 \\ I i 2000 10,000 15,000 20,000 30,000 40,000 50,000 400,000 Approximate Time (sec)

)

h5

Large Break LOCA LTC Calculation i

a WCOBRARRAC a a Extended LBLOCA CMT Analysis Draining IRWST U Injection

. Im.tla.l V Conditions j V i From _WGOTHIC:

-WCOBRA/ TRAC 1. Containment Pressure m

i Long Term Coolm.g -

1 Model Input 2. Sump Levels

3. Sump Temperatures U
Select Window Mode Times and
Boundary Conditions Case 3, Set II Case 3, Set III WC/T WC/T i LTC LTC Calc Calc o o Chapter 15.6 SSAR (RCS & Core Conditions)

< cW\workuiccalc pre 031897 ses

/+

i AP600 SSAR LONG-TERM COOLING WINDOW MODEL ANALYSES _

O '

CASE 3 - LARGE COLD LEG (DECLG) BREAK SET I - CONTINUE SHORT-TERM TRANSIENT WITH CMT INJECTION TO BEYOND ADS 1-3 INJECTION LEVEL t

SHOWS CONTINUED COOLING BY CMT INJECTION AFTER ACCUMULATORS ARE EMPTY LESS AVAILABLE HEAD PRESENT THAN EXISTS ONCE THE IRWST BECOMES AVAILABLE SET 11 - WINDOW CONSIDERS IRWST INJECTION AT A TIME WHEN THE SUMP HAS FILLED TO A LEVEL TO WITHIN THE PERIMETER OF THE BROKEN COLD LEG Fall ONE ADS-4 FLOW PATH t

SET lli - WINDOW CONSIDERS INJECTION FROM AN IRWST REFILLED WITH CONDENSATE RETURN FROM THE CONTAINMENT GUTTERS SENSITIVITY TO GUTTER OPERATION (RAI 440.155 RESPONSE)

/cm/451rmk wpt Page 15

CONCLUSIONS THE WCOBRA/ TRAC WINDOW MODE ANALYSIS METHODOLOGY IS A VALID TECHNIQUE TO CALCULATE ECCS PERFORMANCE OF AP600 '

DURING LONG-TERM COOLING  :

INPUT IS PRESCRIBED SO AS TO OBTAIN A CONSERVATIVE .

ANALYSIS RESULT i

LOW CONTAINMENT PRESSURE HIGH SUMP TEMPERATURE ~

MAXIMUM FLOW RESISTANCES IN PXS COMPONENTS APPENDIX K DECAY HEAT WINDOWS SELECTED FOR THE SSAR LOCA ANALYSIS INVESTIGATE BOUNDING SCENARIOS i

i

/cm/451rmk wpf Page 16

i li!!Tiy ne;

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PRESENTATION TO UNITED STATES 1

NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS i

AP600 LONG TERM COOLING DR. L. E. HOCHREITER SYSTEMS ANALYSIS ENGINEERING  ;

WESTINGHOUSE ELECTRIC CORPORATION (412) 374-5158

/cm/460LEH.wpf Page 1  !

I l l Nil""!!d[

! CONCLUSIONS Lj j

- AP600 LONG TERM COOLING IS A QUASI-STEADY . r40 CESS i

" WINDOW MODE" APPROACH IS AN APPROPRIATE METHOD FOR LONG TERM COOLING ANALYSIS WC/T ANALYSIS OF THE LONG TERM COOLING TESTS USING THE WINDOW MODE APPROACH INDICATES:  ;

VESSEL COLLAPSED LEVEL IS CONSERVATIVELY PREDICTED TOTAL VESSEL INFLOWS, OUTFLOWS, AND PRESSURES ARE PREDICTED WITHIN THE DATA UNCERTAINTY

- APPENDIX K METHODOLOGY USED FOR THE AP600 PLANT ,

CALCULATIONS PROVIDES ADDED CONSERVATISM A CONSERVATIVE RESPONSE OF THE AP600 PASSIVE SAFETY SYSTEM PERFORMANCE IS OBTAINED FOR THE LONG TERM COOLING TRANSIENT

N 1

4 i

s Enclosure I to Westinghouse Letter NSD-NRC-97-5082 April 23,1997 l t

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