ML20049J224

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Affidavit Re Status of Westinghouse Owners Group Response to NRC Items 1.C.1 & 11.K.3.30.Guidelines & Procedures Proposed in Response to Item 1.C.1 Will Improve Operator Ability to Respond to Transients.W/Certificate of Svc
ML20049J224
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 03/10/1982
From: Cadek F
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC), WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20049J217 List:
References
TASK-1.C.1, TASK-2.K.3.30, TASK-TM NUDOCS 8203120278
Download: ML20049J224 (8)


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In the Matter of '.* Pi.

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Docket Sos. 50-445 $m!Il. :h dE5 M,U D' '. -Bib.

TEXAS UTILITIES GENERATING $ .., 50-446 ylis ' 4 D{f" $ f COtPANY, et 41 -

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. .c~ (Application for 76.F Operating 1.icertses)W.1W.8,, j.@'

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OWNERS GP4UP RESPONSE TO Nitt ACTION -

PLAN IT9tS -I.C.1 AMD II.f.L30 4.

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I Frederick F. Cadek, being. first duly sworn, do depose and9e: .' ~

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I an employed by Westinghouse Electric Corporation in the position of. .

., 7 Manager. Safeguards EngineePing ami Develoinenti As such, I have .

i-knowledge of the Westin@cuse and Westinghouse hers Group ("WOG"T.'

response to NRC Action Plan Itses I.C.1 and II.k.3.30 '

'and the status of Westinghouse and WOG efforts in those areas. A statement of my educa-tional and professional qualifications is attached to this affidavit ~.

In this affidavit i address the efforts and cosmitments made by ,

Westinghouse and M0G to respond to NRC Action Plan Items I.C.1 and II.K.3.30. Iraddition. I will describe the measures which recain to be taken 5y Vesting!cuse and WG to cosplete their response 'a those 2 Action Plan Items.

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  • This is a telecopy racsimile. A copy of the original and attachments will be transmitted to the parties tomorrow.

8203120278 820310 PDR ADOCK 05000445 O PDR

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. ,. i ACTION PLAN ITEM I.C.1 Y/!M  ; ::d g , ;p,g.; > - m -

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This Item provides that< applicants for Operating Licenses perforu '

g, . .: 2-analyses of transients and accidents, prepara emergency procedure guide-

! lines, upgrade energency procedures, ard corduct(6perator refraining.

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g T~ne purpose of the' 4. wied transient and accident analyses is to provide an increase in safety by fsproving the performance oh reactor i operators during transient and accident conditions. The analyses that

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support guideline and procedure development are to censider, therefore, the occurrences of multiple and conseques;tial failures. The provisions of this Itcs are described in. detail in IUREG-0737, titled "Clarifica-f tion of lWI Action 71an Requirements' (November 1980), at p. I.C.1-1. .

The iiGG submitted a detailed description of the program lto neet the provisions of Item I.C.1 by letter CG-61 dated July 7,1981 (fres Jurgenson to Hanauer) (copy attached). The NRC accepted'that proposed 1 progran for respcading to Ites I.C.1 by letter of September 18, 1981 (frc= Eisenhut to Jurgenson) (copy attacted).

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k In accordance with this program, the WOG supplied to the MRC emer-1 5

gency response guidelines based upon analyses of various LOCA and non-h LOCA transients. See letter OG-M from Robert W. Jurgenson (Chair: nan, e

i WGG) to D. G. Eisenhut (Director, Division of Licensing, Office of MRR, w

H y Nuclear Regulatory Cannission), dated November 30, 1981. Mditional e

(; esergency response guidelines am to be submitted in June,1982. The l

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mitted and posed certain questions to WOG as a: result of. theibAreview at "%

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guidelines and -, sy r,hres in accordance with Itemict were

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sutaitted to the NRC'irt numerous WOG submittals. These anal.pses include ,

. r- j; transient analyses in KAP-9601, WCAP-9754, EAP-9744, and WCAP-9639.

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The emergency response guidelines include background sections which pro-

e vide additional trarsient analysas as a basis for the guiMfmes. The criteria for establishing a. basis for selecting mitiple failures in the guidelines is presented in WCAP-9691 and WCG 1eiiter OG-54 dated March 18, 1981 (from Jurgenson to Hanauer) (copy attached). Based on the guide--

lines and procedures proposed in response to this Iten, the ability'of operators to respond properly to transients will be improved.. 'Further, current operator training programs will be enhanced by additional in-sight iato the course of events likely to be encountered during a

! transient.

ACTION PLAM ITEM II.K.3.30 This Action Plan Its provides that NSSS vendors revise, document .

and submit to MRC for approval their small-break LOCA analyses upon taking into account and comparing results with experiser.tal data, in-cluding data fra the LOFT and Seniscale tests. The purpose of this b

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exercise is to provide assursace that' .the small-break LOCA sodels are *

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acceptable to calc:tlate the behavior and consequences ofissaM- primary l . p. n.-

systen breaks. .E l 4;i.. .

Westinghouse believes that:;the small-break LOCA analysis model i

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j- currently approved by the patC'$taff for use on Westinghouse designed MSSS (and used in the small-brsiat" LOCA analysis for Comanche Peak) is s.t" .

conservative and in compliance {with Appendix K of 10 C.F.R. Part 50 and 10 C.F.R. Section 50.46. d, Westinghouse believes that improve.-

. v' ment in the reaMsm of small break calculations is a wort!ndfle effort

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and thenfore has coanitted to revise current small break models.

.5 l A detailed outline of the' scape and schedule of the Westinghouse i a.

I plan to revise the Appendix K sma!I-breat LotA analysis model is set forth in letter MS-TM-2318 dated September 26,1980 (from T. M. Anderson, Manager, Nuclear Safety Department. Westinghouse Electric Corporation to Eisenhut) (copy attached). Westinghouse has coanitted to submit a draft report on its nvised model to the NRC by April 1,1982 in letter MS-EPR-2524" dated November 25,1981 (from E. P. Rahe, Planager Nuclear 5afety Department. Westinghouse Electric Corporation to Eiserthut) (copy attached). :

As part of this effort, Westinghouse has performed blind test pre-

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I dictions of LOFT experiments for verification of the total model. The ccuparisen of these predictions with the test results, taking into account variations in input data and system configuratics, indicates that the Westinghouse nodel has conservatively predicted important P

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Subscribed and sworn to before ne this 10th day of March 1982.

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h' l Educational and Professional Qualifications

( . FREDERICX F. CADEK }

  • j MANAGER - SAFERWtDS EEIMEERING MD.TVELOPMENT l MUCLEAR TEQiMCLOGY DIVISICN l -

My name is Frederick F. Cadek. My business address 'is liestinghouse l Electric Corporation, P. O. Box 355 Pittsburgh, Pennsylvania 15230. I f as employed as Manager, Safeguards Engineering and Development at the f Nuclear Technology Division for ilestinghouse Electric Corporation and I l* have served in this capacity since July 1981. I.as responsible for the

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f analysis of large and small break Loss of Coolant Accidents (LOCA) to ,

verify the effectiveness of Emergency Core Cooling Systems (ECCS) for ,

nuclear power plants. % responsibilities also -include the development of analytical metrods, models and experiments which develop and verify the camouter codes used to perfom these analyses. These analyses are ..

used to provide input to plant safety Analysis Reports as well as the .

basis for developsect of Em~py Response Guidelines.

I was graduated frca the University of introit in 1961 with a B.S. Degree in Mechanical Engineering and from Marthwestern University in 1963 with a M.S. Degree in Mechanical Engineering. I have also received a Ph.D. Degree .in Mechanical Engineering from the University i of Cincinnati in 1968. l,9 Q.

Since joining Vestinghouse in 1968 I have had assignments directly involved in nuclear power, both as a technical group manager and as a progran manager. Thehsignments include hager of Themal-Hydraulic Development, Manager of Thernal-Hydraulic Design. and Manager, Major

[ Programs, both in the Itaclear Fuel Division and Nuclear Technology Divisicn. (

e UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

TEXAS UTILITIES GENERATING ) Docket Nos. 50-445 COMPANY, et- al. ) 50-446

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(Comanche Peak Steam Electric ) (Application for Station, Units 1 and 2) ) Operating License)

CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing

" Applicants' Answer to CFUR's Motion for Voluntary Withdrawal and Response to Board Invitation for Views on Contentions", in the above-captioned matter were served upon the following persons by deposit in the United States mail, first class postage prepaid this 10th day of March, 1982:

Marshall E. Miller, Esq. Chairman, Atomic Safety and Chairman, Atomic Safety and Licensing Appeal Panel Licensing Board U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C. 20555 Washington, D.C. 20555 Dr. Kenneth A. McCollom Marjorie Ulman Rothschild, Esq.

Dean, Division of Engineering Office of the Executive Architecture and Technology Legal Director Oklahoma State University U.S. Nuclear Regulatory Stillwater, Oklahoma 74074 Commission Washington, D.C. 20555 Dr. Richard Cole, Member Atomic Safety and Licensing David J. Preister, Esq.

Board Assistant Attorney General U.S. Nuclear Regulatory Environmental Protection Commission Division Washington, D.C. 20555 P.O. Box 12548 l

Capitol Station Chairman, Atomic Safety and Austin, Texas 78711 Licensing Board Panel U.S. Nuclear Regulatory J. Marshall Gilmore, Esq.

Commission 1060 W. Pipeline Road Washington, D.C. 20555 Hurst, Texas 76053

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l Mr. Richard Fouke Mr. Chase R. Stephens 1669-B Carter Drive Docketing & Service Branch Arlington, Texas 76010 U.S. Nuclear. Regulatory Commission Mrs. Juanita Ellis Washington, D.C. 20005 President, CASE 1426 South Polk Street Dallas, Texas 75224 l'

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William A. Horin a

cc: Homer C. Schmidt Spencer C. Relyea, Esq.

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