ML20236A490
| ML20236A490 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 10/14/1987 |
| From: | Alexion T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8710220294 | |
| Download: ML20236A490 (7) | |
Text
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? ? October 14, 1987
' Docket No. 50-483
%.Docret Distribution:
g11e n @ EJordan NRC & Local'PDRS JPartlow PDIII-3 r/f TBarnhart GHolahan Wanda Jones '
PKreutzer- EButcher '
LICENSEE: Union. Electric DWigginton .ACRS(10)-
KPerkins GPA/PA FACILITY: Callaway Plant 0GC-Bethesda ARri/LFMB DHagan Grey File !
SUBJECT:
SUMMARY
OF MEETING WITH UNION ELECTRIC REGARDING THE TRANSITION CORE DNBR PENALTY FOR CYCLE 3 On~0ctober 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- i pants at the meeting are listed in Enclosure 1. The licensee's letter documenting their: findings is provided in Enclosure 2. Nonproprietary 1 slides used during the n'eeting are in Enclosure 3. The proprietary slid (s '
used during the meeting are being withheld from public disclosure under 10 CFR C.790 of the Commissions 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 ccre 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 Merch 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.
/
Thomas W. Alexion, Project Manager Project Directorate III-3 Division of Reactor Projects
Enclosures:
i
- 1. Participants l
- 2. Licensee's letter
- 3. Non proprietary slides (proprietary slides withheld - 2.790) cc: See next page j Office: LA/PDIII-3 P.Mf fjL-3 GC PD/PDIII-3 Surname: PKreutzer TAl(ic K h/rl DWigginton Date: 10/ /87 10/ly /87 / 87 10//f/87 i
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%" 4 ASHINGTON, D C.20555 3 '/.,a/
' Sp. .V -October 14, 1987 i
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Doc ht ho. 50-483 "
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E su MATER:AL Decontrolled when separated from enclosures. 4 LICENSEE: Union Electric '
FACILITY: Callaway Plant w_ . . -
SUBJECT:
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 Comissions 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 i provided in the original reload submittal (dated March 31,1987) remain J valid.
The staff indicated that this new iiifonnation will be included in the review of the reload application. The staff did not identify any outstanding issues at tie meeting.
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Thomas W. Alexion, Proj t Manager i Project Directorate III-3 Division of Reactor Projects
Enclosures:
- 1. Participants
- 2. Licensee's letter
'3. Non proprietary slides (proprietaryslideswithheld-k.79C) cc: See next page Enclosure (s) contain(s) ;
I 10 CFR 2.7E MATERIAL Decontre!!ad when separated from enclosures.
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Mr.>0. F.'Schnell Callaway Plant ~
Union Electric Company Unit No..I Cc:
Dr..J. 0. Cermack
. Mr. Bart D. Withers !
CFA'Inc. President and Chief 4 Professional Dr., Suite 110- Executive Officer '
Gaithersburg, MD 20879 Wolf Creek Nuclear Operating i Corporation ;
Gerald.Charnoff, Esq. F. O. Box 411 '
Thomas A. Baxter, Esq. Burlington, Kansas 66839 Shaw, Pittman, Potts & Trowbridge 2300 N Street, N. W. Mr. Dan I. Bolef, President Washington, D. C. 20037 Kay Drey, Representative q Board of Directors Coalition '
. Mr. T. P. Sharkey for the Environment Supervisor, Compliance St. Louis Region Union Electric Company 6267 Delmar Boulevard ,
Post Office Box 620 University City, Missouri 63130 Fulton,-Missouri 65251 j U. S. Nuclear Regulatory Commission ,
Resident Inspectors Office -
RR#1 Steedman, Missouri .65077
.Mr. A1an C. Passwater, Manager Licensing'and Fuels Union Electric Company i Post Office Box 149 i St. Louis, Missouri 63166 Manager - Electric Department Missouri Public Service Comission 301 W. High
" Post Office Box 360
-Jefferson City, Missouri 65102 i
Regional Administrator i U. S. NRC, Region III !
799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Ronald A.-Kucera Deputy Director Department cf Natural Resources P. O. Box 176 ,
siefferson City, Missouri 65102 I
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3-Enclosure ~l
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j TRANSITION CORE DNBR' PENALTY MEETING !
7 OCTOBER 6, 1987 ATTENDANCE LIST NAME ORGANIZATION.
~
T. Alexion NRC/PD III-3 M. Hodges NRC/SRXB L..Phillips NRC/SRXB ;
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 K. Mc Atee W/ Thermal-Hydraulic Design E. Novendstern W/ Thermal-Hydraulic Design !
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. .g ts01 Grenot Street, St. Louk Densigt f. Sohnell woe PresWent October 6, 1987 l
U.S.-Nuclear Regulatory. Commission
' ATTN:- Document Control Desk washington, D.C. 20555. !
Gentlemen: ULNRC-1643 DOCKET NUMBER 50-483 i
CALLAWAY PLANT REVISED VANTAGE 5' TRANSITION CORE EFFECTS FOR CYCLE 3 l
References:
- 1) .ULNRC 1470 dated March 31, 1987 1 2)- Westinghouse Letter NS-NRC-87-3260 dated October.2, 1987 from W. J. Johnson to i M. W.'Bodges (
I 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 l Electric referenced WCAP-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 5 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 conclus; ons 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 magnitude of the DNB transition core penalty continues to be offset by tha' margin which is maintained between the design and safety limit DNBRs made available due to the improved DNB l Performance of the IFM grids described in WCAP-10444. The VANTAGE 5 DNB transitien 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 DNS margin are provided in the suelosed replacement pages to Reference 1.
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Adethe Actesse: P.O. mar f 49, St. Loue, MO s3f 86
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I The results of the significant Nazards Evaluation transmitted by Reference 1 remain unchanged. If there are any L
questions with respect to this subject, please contact us.
l Very truly yours, Donald F. Schnell DS/kea Attachments: ULNRC-1470, dated March 31, 1987, Replacement Pages
. 1) Attachment 1, Safety Evaluation, Page 17
- 2) Attachment 2, Technical Specification Changes, Bases page B3/4.2-4
- 3) Attachment 3, References, page 40 1
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i STATE OF MISSOURI )
) ss CITY OF BT, LOUZB )
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 i knows the content thereofs that he has executed the same for and on !
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.
By 'Af Donald F. 5thne J
. l Vice President !
Nuclear SUBSCRIBED and sworn to before me this N day of !8/%> ,198 7,
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- unuurim/ #T !
NOTARY PUBUC. STATI of MisS00m NY COMW$$10N IXPlRES APRIL 22.1000 ST. L0 ult COUNTY.
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. . . 1 cc: Gerald charnoff, Esq.
Shaw, Pittaan, Potts & Trowbridge 2300 W. Street, N.W.
Washington, D.C.' 20037 Dr. J. O. Cermak !
1CFA, Inc.
4 Professional Drive (Suite 110)
Gaithersburg, MD 20879 W. L. Forney Chief, Reac':or Project Branch 1 .
U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road
- Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RR$1 Steedman, Missouri 65077 Tba Alesion (2)
Office of Nuclear Reactor Regulation l U.S. Nuclear Regulatory Commission Mail 8 top 316 7920 Norfolk Avenue Bethesda, ND 20014 Ron Rucera, Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, M0 65102 ,
Manager, Electric Department
- Missouri Public Service Commission P.O. Box 360' Jefferson City, MO 65102 i
ATTACHMENT 1 follows. A fraction of the marDin is utilized to accomodate the transition core DNBR penalty (2% for DFA 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 L'ANTAGE 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 desigm The VANTAGE 5 transition core penalty is discussed in References 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 bowing, as described in Reference ll, must be accounted for in the DNBR safety snalysis of Condition I and Condition Il events for each plant application. Applicable generic credits for margin resulting from retained conservatism in the evaluation of DNBR and/or margin obtained from measured plant oparating parameters (such as FfH or core 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 accoenodate full-flow and low-flow DNBR penalties.
The transition core DNB methodology given in References 2 and 17 has been l approved by the NRC via Reference 18. Using this methodology, transition cores are analyzed as if they were full cores of one assembly type (full 0FA i or full VANTAGE 5), applying the applicable trar.sition core penalties of two percent for DFA 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 per.alty, i
The fuel temperatures for use in safety analysis calculations for the VANTAGE 5 fuel are the same as those used for the DFA fuel. Westinghouse uses the PAD fuel performance code, Reference'6, to perform both design and licensing l calculations. When the code is used to calculate fuel temperatures to be used as initial conditions in sefety analyses, a conservative thermal safety model, Reference 7, is used.
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. . ULNRC-1643 f Attachmant 2 l e ..... RAlt5 _
"""""'"'N 3/4.t.2 and 3/4J 3 NEAT FLUX ICT CHANNEL FACTOR AND NOCLEAA DmiAlpY A!$E _
nor m m n.=m (Gontinued) l Each of tagsse is measurable but will normally onl 1 ically as spe:19ted in Specifications 4.2.2 and 4.t.3.This y beperiodic determined period-surveil-lance is suffic$nt to ensure that the limits are maintained provided:
- a. Cent 1 tods in a si e group move together with no indiNdual roi sortion differi by more than i 12 steps indicated from
,the p demand posit on.
g.
l b.
Cantgel red banks are sequenced with overlapply groups as described im Spification 3.1.3.5. ~
- c. The entrol rod insertion Itaits of specification 3.1.3.8 ers maln$$aed. .
- d. The sial power distribution, expressed in terms of AX1AL FLUX ,
D@, is amintained within the limits.
1 b witl maintained within its 1 ned. The m1anatten of its providr,J condittens a. through d.
as a furstion of THEIDIAL p0WER above em matn elleWs'sheness $4e podial peWor shape all permissible rod insertion limits. j When an Fi measurement is taken, an allowance for both experimental error l and aangfoctaril s tolerance must be ande. As alleennce of 85 is appropriate for l a full.eere nesp taken with the 1ecore detector flux mapping system and a 35 l allemence is'. appropriate for annufacturing televersce.
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When is measured. (i.e.. inferred). no additional allowances are !
necessary p r to souparison with the limits of section 3.2.3. An error allow- I ance of 45 has apen included in the limits of Section 3 3.3. 3E
/2.5 7e --
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Margin be n the safety 1ysis ON5R limits Optimited fuel inble and 1 sells respectively(1.42 and
, and 1.61 andT.'45 1.69 for for ~the tw WNTAet 5 able and 1.32 and 1.34 for the staed fuel cal tablecells),and and typical thecellsdesign and 1.32DNBR and 1. linits (33 for the VANTA8E 5 thf and typt 1 eells, respectively) is asintained. A draction of this mareta a util > accommodsta the transition core ONBR penalty -
(25 for Optisited fue "
'or VAltrast 5 fuel) and th appropriate fuel rod l bow ON5R penalty (lessV.; t.55 per WCAP 4691. Rev.1. The margin between -
. . des.1 n and safety anM.Wis ONER limits of 75 for Optia med fuel and 185 for VANT fuel includes greater than 35 raergin for Optimited fuel and p::t=
4/% rgin for VAGAGE 5 fuel for plant design flexibility.
- l The ho? channel factor (a)isF.masuredperiodicallyandincreasedby a cycle and asieht dependent r factor appropriate to either ehems) Operation i
or RESTRICTES AFD OPERATION.
limit on the het channel facter, k(or 1.) isW(z)N.W(a)go to pr9 accounts vide assurance that the for the effects CALLAMAY = UNIT 1 53/4t-? Amendment No. M.
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ATTACHMENT 3
. 22. Lee, N., Rupprecht, S. D., Schwartz, W. R., Tauche, W. D., " Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code " WCAP-10054-P-A (Proprietary) and WCAP-10081-A (Non-Proprietary) August 1985.
- 23. Esposito, V. J., Kesavan, K., and Naul, B. J.; "W-FLASH-A Fortran-IV Computer Program for Simulation of Transients in a Nulti-Loop PWR,*
WCAP-8200 (Proprietary), July 1973.
- 24. Neyer, 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
' Addendum 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 Transition Core Effects".
- 28. ULNRC - 1643 dated October 6, 1987, " Revised Vantage 5 Transition Core Effects for Cycle 3".
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- ~o Enclosure 3 CALLAWAY CYCLE 3 LICENSING MEETING NRC/ UNION ELECTRIC / WESTINGHOUSE l OCToEER 6, 1987 I. INTRODUCTION -
UNION ELECTRIC o BACKGROUND AND PURPOSE OF THE MEETING
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II. 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 ,
y 5
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I CON C _US ON EFFECT OF SMALL INCREASE IN THE VANTAGE 5 TRANSm0N CORE PENALTY DOES NOT ALTER ## CONCLUSIONS REPORTED D
IN'BOTH THE CAllAWAY UCENSING SUBMITTAL AND WCAP-10444.
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