ML20236A486

Summary of 871006 Meeting W/Util & Westinghouse to Discuss Transition Core Departure from Nucleate Boiling Ratio Penalty for Cycle 3 Operation.Attendee List,Util Ltr & Proprietary & Nonproprietary Viewgraphs Encl

ML20236A486
Person / Time
Site:	Callaway
Issue date:	10/14/1987
From:	Alexion T Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
Shared Package
ML19304B612	List: ML20236A486
References
NUDOCS 8710220294
Download: ML20236A486 (3)

Text

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ft 'q UNITED STATES 7"'

( f ,,n NUCLEAR REGULATORY COMMISSION d 3 $ WASHING TON, D. C. 20S55 t, . .E October 14, 1987

1. 0 L . Docket ho. 50-483 l C

li u n 2. a0 MATERIAL Decontrohd )

when separated from enclosures.

LICENSEE: Union Electric FACILITY: _ Callaway Plant

SUMMARY

OF MEETING WITH UNION ELECTRIC REGARDING THE TRANSITION CORE DNBR PENALTY FOR CYCLE 3 On October 6, 1987, the licensee and representatives from Westinghouse met with the staff to discuss the transition core departure from nucleate boiling ratio (DNBR) penalty for Cycle 3 operation at Callaway. Partici-pants at the meeting are listed in Enclosure 1. The licensee's letter documenting their findings is provided in Enclosure 2. Nonproprietary slides used during the meeting are in Enclosure 3. The proprietary slides used during the meeting are being withheld from public disclosure under 10 CFR 2.790 of the Connissions regulations.

The licensee stated that as a result of a generic assessment which affects the magnitude of the Vantage 5 DNBR transition core penalty, an evaluation was performed for Callaway Cycle 3 which indicated the need for a small (1.5 percent) increase to the DNBR transition core penalty. However, the licensee stated that the small increase continues to be offset by the margin which is maintained between the design and safety limit DNBR's, and that the safety evaluation and significant hazards evaluation conclusions provided in the original reload submittal (dated March 31,1987) remain valid.

The staff indicated that this new information will be included in the review of the reload application. The staff did not identify any outstanding issues at the meeting.

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Mhfal& v< lI Thomas W. Alexion, Proje t Manager Project Directorate 111-3 Division of Reactor Projects

Enclosures:

1. Participants DESIGNA ED ORlGINAL: .. /

2. Licensee's letter \

3. Non proprietary slides CMilied By- / ~~--- '

(proprietary slides withheld - 2.790) cc: See next page Enclosure (s) contain(s)

.10 CFR 2.E^ MATERIAL Decontrc!!ed 1 EA 2288M 8U>8! dea when separated from enclosures.

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'.I Mr. D. F. Schnell- Callaway Plant Union Electric Company Unit No. 1 l

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! Dr. J. O. Cermack- Mr. Bart D. Withers CFA Inc. President and Chief =

4 Professional Dr., Suite 110 Executive Officer I

' Gaithersburg, MD 20879 Wolf Creek ' Nuclear Operating .l

. Corporation' .)

Gerald Charnoff, Esq. P. O. Box 411  ;

Thomas A. Baxter, Esq.

Shaw, Pittman, Potts & Trowbridge Burlington, Kansas 66839 l

2300 N Street, N. W. 'Mr. Dan I. Bolef, President Washington, D. C. 20037 Kay Drey, Representative Board.of Directors Coalition Mr. T.:P. Sharkey for the Environment Supervisor, Compliance St. Louis Region Union Electric Company 6267 Delmar Boulevard 1 Post Office Box 620 University City, Missouri 63130 ,

Fulton, Missouri 65251 l U. S. Nuclear Regulatory Commission Resident Inspectors Office RR#1 Steedman, Missouri 65077 i

Mr. Alan C. Passwater, Manager  !

Licensing and Fuels

-Union Electric Company Post Office Box 149 St. Louis, Missouri 63166 Manager - Electric Department Missouri Public Service Comission 301 W. High Post Office Box 360 Jefferson City, Missouri 65102 Regional Administrator U. S. NRC, Region III )

799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Ronald A. Kucera, Deputy Director Department of Natural Resources ,

- P. O. Box 176 l Jefferson City, Missouri 65102 l l

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Enclosure 1 TRANSITION CORE DNBR PENALTY MEETING )

OCTOBER 6, 1987 l- -

ATTENDANCE LIST l

NAME ORGANIZATION-T. Alexion NRC/PD III-3  ;

! M. Hodges- NRC/SRXB l L. Phillips NRC/SP.XB W. Brooks NRC/SRXB F Orr NRC/PDI-4 A. Passwater UE/ Licensing & Fuels W..Bobnar UE/ Licensing & Fuels K. Connelly UE/ Licensing & Fuels P. Loftus W/ Nuclear Safety ..

4, K. Mc Atee W/ Thermal-Hydraulic Design 1 E. Novendstern W/ Thermal-Hydraulic Design  !

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Enclosure 2 t901 Grealot Street St. Lode ConsM f. Schnell Woe Prseident October 6, 1987 U.s. Nuclear Regulatory Commission ATTN Document Control Desk Washington, D.C. 20555 Gentlemen: ULNRC-1643 DOCKET NUMBER 50-483 CALLAWAY PLANT REVISED VANTAGE 5 TRANSITION CORE EFFECTS FOR CYCLE 3

References:

1) ULNRC 1470 dated March 31, 1987

2) Westinghouse Letter NS-NRC-87-3268 dated October 2, 1987 from W. J. Johnson to M. W. Bodges Reference 1 transmitted the Reload License Amendment Application for callaway Plant using Westinghouse 17 x 17 VANTAGE 5 fuel assemblies. As part of the application, Union Electric referenced NCAP-10444-P-A, " Westinghouse Reference Core Report, VANTAGE 5 Fuel Assembly" as the-approved methodology for assessing the transition to VANTAGE 5 fuel.

Westinghouse has recently completed an assessment which affects the magnitude of the VANTAGE $ DNB transition core  ;

penalty. The results of this generic assessment were provided to (

NRC via Reference 2. An evaluation has been performed for Callaway Cycle 3 which demonstrates the safety evaluation  ;

conclusions presented in Reference 1 remain valid, but in'dicates )

the n'eed for a small (1.5 percent) correction to the magnitude of the DNB transition core penalty. The small increase in the q magnitude of the DNB transition core penalty continues to be i offset by the margin which is maintained between the design and safety 1 hit DNBRs made available due to the improved DNB performance of the IFM grids described in WCAP-10444 The VANTAGE 5 DNB transition core penalty increases from 11 percent to 12.5 percent and the DNB margin decreases from 5.5 percent to 4 percent. The revised transition core penalty and revised DNB l margin are provided in the enclosed replacement pages to Reference 1.

' Y Meane A6ttene: Fo. non 149, st. Loun, MO s3166 N N *N ,

EG:0T 48/90/0T

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The results of the Significant Hazards Evaluation transmitted by Reference 1 remain unchanged. If there are any questions with respect to this subject, please contact us.

Very truly yours, Donald F. Schnell DS/kea Attachments: ULNRC-1470, dated March 31, 1987, Replacement Pages

1) Attachment 1, Safety Evaluation, Paga 17 Attachment 2, Technlcal Specification Changes, 2)

Bases page B3/4.2-4

3) Attachment 3, References, page 40 I

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STATE OF MI5800RI')

. )- as CITY OF ST. LOUIS )

Donald F. Schnell, of lawful age, being first duly sworn upon oath says that he is Vice President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and

'knows the content thereof; that he has executed the same for and on 1 I

behalf of said company with full power and authority to do so; and

'that the facts therein stated are true and correct to the best of his knowledge, information and belief.

Sy d J Donald F. 5thnell ,

Vice President .

Nuclear

' SUBSCRIBED and sworn to before me this b day of  ![MV , 198 '/.

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hJ's>A. l BAR8 ARA (PFM 8 i N0fARY PUBUC. STATI Of Miss00m m couwssion wints APAn 22. taas

87. Loull COUNTY.

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- _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ . _ A Oh w opg fj Q M sg

9 cc Gerald Charnoff, Esq. .

f, haw, Pittman, Potts & Trowbridge M300 N. Street, N.W.

Washington, D.C.' 20037 Dr. J. O. Cermak CFA, Inc. i 4 Professional Drive (suite 110)

Gaithersburg, MD 20879 W. L. Porney Chief, Reactor Project Branch 1 .

U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road i Clen Ellyn, Illinois 60137 Bruce Little 2 Callaway Resident office U.S. Nuclear Regulatory Commission i

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steedman, Missouri 65077 Tom Alexion (2)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 316 j 7920 morfolk Avenue Bethesda, MD 20014 .

Ron Rucera, Deputy Director Department of Natural Resources P.O. Box 176 1 Jefferson City, MO 65102 Manager, Electric Department

. Missouri Public Service Commission ,

P.O. Box 360' Jefferson City, MO 65102 l

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ATTACHMENT 1 l

follows. A fraction of the margin is utilized to accomodate the transition-

core DNBR penalty (2% for OFA fuel and 12.5% for VANTAGE 5 fuel) and the appropriate fuel rod bow DNBR penalty, Reference 11, which is less than 1.5%.

The existing 7% margin in the DFA fuel and 18% margin in the VANTAGE 5 fuel between the design and safety analysis DNBR limits also includes a greater  ;

than 3% DNBR margin in the DFA fuel and 4% DNBR margin in the VANTAGE 5 fuel reserved for flexibility in the design. The VANTAGE 5 transition

core penalty is discussed in Refe'rences 27 and 28. .

The LOPAR, and 0FA, and VANTAGE 5 designs have been shown to be hydraulically compatible in Reference 1. ,

The phenomenon of fuel rod bowir.g; e, described in Reference 11, must be accounted for in the DNBR safety analysis of Condition I and Condition II i events for each plant application. Applicable generic credits for margin 1 resulting from retained conservative in the evaluation of DNBR and/or margin j obtained from measured plant operating parameters (such as F,"H or core j flow) which are more restrictive than those required by the plant safety analysis, can be used to offset the effect of rod bow. The safety analysis for the Callaway Plant maintains sufficient margin between the safety analysis limit DNBRs and the design limit DNBRs to accomodate full-flow and low-flow DNBR penalties.

The transition core DNB methodology given in References 2 and 17 has been approved by the NRC via Reference IB. Using this methodology, transition cores are analyzed as if they were full' cores of one assembly type (full 0FA or full VANTAGE 5), applyin,g the applicable transition core penalties of two percent for OFA fuel and eleven percent for VANTAGE 5 fuel. The safety analyses for the Callaway Plant maintains sufficient margin between the safety analysis limit DNBRs and the design limit DNBRs to accomodate the transition core DNBR penalty and the appropriate rod bow DNBR penalty.

The fuel temperatures for use in safety analysis calculations for the VANTAGE 5 fuel are the same as those used for the OFA fuel. Westinghouse uses the PAD fuel performance code, Reference 6, to perform both design and licensing calculations. When the code is used to calculate fuel temperatures to be used as initial conditions in safety analyses, a conservative thermal safety model, Reference 7, is used, wA

. . . ULNRC-1643

. Attachment 2 RA$ts __

_ '""*"*"" b - - -

3/4.2,2 and 314.2.3 NEAT FLUX NOT CHANNEL FACTOR AND MUC1. TAR ENTHALPY R!$t --

ngT ="5_ h am (Goritinued) , , , g Each of tigese is measurable but will normally onl ically as spe:19ted in Specifications 4.2.2 and 4.2.3. y This be detemined period-periodic surveil.

Iance is suffic$pnt to ensure that the limits are ma,intained provided:

a. Cent 1 tods in a single group move together with no individual ref sortion differiac by more than +"' 12 steps. indicated, from

.the p demand posit <on.

I lh b. Can 1 red banks are sequenced with overlapping groups as described j

F in ification 3.1.3.5. -

c. The entrol rod insertion limits of Specification 3.1.3.8 are anta$$ned.. -.

d. The miel power distribution, expressed in terms of AX1AL FLUX

.- D @-, is maintained within the limits.

dwiT) maintained within its 1 its provided conditions a. through d.

eb6ve aM antn ned. The relaxath of as a function of THUMAL POWER allows'sheness , the radial power shape

. all pesissible rod insertion limits.

Whe6 an FE measurement is taken, an allemence for both experimental errer ene yngrecturil s tolerence must'be ande. An allowance of 55 is appropriate for a ful .coes anp taken with the incers detector flux mapping system and a 35 allemnce is . appropriate for annufacturing tolertnee.

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When isseasured.(i.e.. inferred).noadditionalallowancesare necessary pr r to comparison with the limits of Section 3.2.3. An error allow-ance of 45- has toen included in the limits of Section 3.2.3. 3E

/2.5 % -~

Margin be n the safety lysis DN5a limits Optimited fuel table and 1 sells respectively(1.42 , and 1.81 and andT.'45 1.69 for for -the cal cells),and the design DNBA limits (1.32 and t w ttWITAtt I able and 1.84 for the mised fuel table and typical cells and 1.32 and 1.33 for the VANTAtt 8 thi and typt 1 sells, respectively) is maintained. A traction j of this enrotn is util >' acsammodata the transition core DNBR penalty 25 for Opt'aised fue "

or VAKTAGE 8 fuel) and th appropriate fuel rod l b(ow DN8R penalty (lessW.. l.55 per WCAp 0691. Rev.1. The margin between -

. . des.1 and safety. analysis M8R limits of 75 for Optia med fuel and 181 for VANT fuel includes greater than 35 margin for Optimized fuel and p::t:5

//% rgin for VANTA415 fuel for plant design flexibility. { l The het channel factor )ismeasuredperiodicallyandincreasedby a cycle and heitht dependent r factor appropriate to either ennal Operation or RESTRICT!B AFD OPERATION.

lief t en the het channel facter,s).k(or is W(t)E. to provide assurance tiat thew (z

-8!)/ c gy,y CALLANAY -  ! 1 3/4t-i Amenenent No. H.

ATTACHMENT 3 l 22. Lee, N., Rupprecht, S. D., Schwartz, W. R., Tauche, W. D., " Westinghouse Small Break ECCS Evaluation Nodel Using the NOTRUMP Code," WCAP-10054-P-A (Proprietary) and WCAP-10081-A (Non-Proprietary) August 1985.

23. Esposito, V. J., Kesavan, K., and Maul, 8. J.; "W-FLASH-A Fortran-IV Computer Program for Simulation of Transients in a Multi-Loop PWR,"

WCAP-8200 (Proprietary), July 1973.

24. Meyer, P. E., "NOTRUMP, A Nodal Transient Small Break and General Network

- Code," WCAP-10079-P-A (Proprietary) and WCAP-10080-A (Non-Proprietary),

August 1985. ,

25. Letter C. E. Rossi (NRC) to E. P. Rahe, Jr. (W), " Acceptance for Referencing of Licensing Topical Report WCAP-10266," November 1986.

26. Letter W. Johnson 3) to J. Lyons (NRC), " Submittal of WCAP-10266 l

' Addendura 1, BASH Power Shape Sensitivity Studies," January 1987.

27. Letter from W. J. Johnson (Westinghouse) to M. W. Hodges (NRC) dated October 2, 1987, NS-NRC-87-3268,

Subject:

" VANTAGE 5 I

Transition Core Effects".

28. ULNRC - 1643 dated October 6, 1987, " Revised Vantage 5 Transition Core Effects for Cycle 3".  :

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Enclosure 3 1

CALLAWAY CYCLE 3 LICENSING MEETING NRC/ UNION ELECTRIC / WESTINGHOUSE OCTOBER 6, 1987 I. INTRODUCTION -

UNION ELECTRIC o BACKGROUND AND PURPOSE OF THE MEETING I

11. CALLAWAY LICENSING ACTIVITIES STATUS AND SCHEDULE OVERVIEW -

UNION ELECTRIC III. VANTAGE 5 DNB TRANSITION CORE EFFECTS o BACKGROUND (INCLUDING GENERAL INFORMATION/

LICENSING STATUS) -

WESTINGHOUSE o THERMAL 8 HYDRAULIC CONSIDERATIONS -

WESTINGHOUSE o LICENSING CONSIDERATIONS -

WESTINGHOUSE IV. CALLAWAY CYCLE 3 LICENSING APPROACH /

ISSUE RESOLUTION -

UNION ELECTRIC V.

DISCUSSION / WRAP-UP

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C0sC _US O N EFFECT OF SMALL INCREASE IN THE VANTAGE 5 TRANSm0N CORE PENALTY DOES NOT ALTER ANY CONCLUSIONS REPORTED IN'BOTH THE CALLAWAY UCENSING SUBMITTAL NiD WCAP-10444.

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