ML17194A601
| ML17194A601 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/30/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Delgeorge L COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8204130478 | |
| Download: ML17194A601 (4) | |
Text
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DlSTRIBlHION:
Docket File NRC PDR L PDR ORB#2 Rdg
.OEisenhut SNorri s JHegner CBerlinger OELD AEOD IE ACRS-10 Gray Fi 1 e Docket No. 50.-249
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Mr. L. DelGeorge 0
... -.. ~~~- J.~ 1982 01 rector of Nuclear L 1 cens1 ng,...,.,_,.... -~.....,.., _,,...,,_,,.-
Commonweal th Edison Company,.... :.;. ~,,,,_, '"~. *---*~...
P. o. Box.767 Chicago, Illinois 60690
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Dear Mr. DelGeorge:
RE:
Dresden Nuclear Power Sta~j_o_n. )!IJ!.t. ~,. _,.,...
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Our evaluation of the Dresden" 3,.. Cyc:J.ELB.R~1.Q.ag su~1~tal -~~t~d ~apuary 11, 198? is continuing. Addit1o11a1 J,~f9rmatio.n )~. n~ces~aryJ_n _.o,r~~r for us to complete our review.
We have prepared the enclosed* ques.~t9n~.P.~r:tq1n1.ng to ~~NF.. ~J-7-6,. *..,,
Dresden Unit 3 Cycle 8 Reload. An~~Y.~!s *. ~evis1cm.1
- Your, ~RC Pr_-Oject...,.
Manager will contact you (ri#gqrdt~.9.~h.~,,rixt~t -~~ped1.en~ me~hod_ ~f. pr<?v1d11)g your response in order not* to.. ~QIP~t:t,.~tt~~r o,yr ev,aJu~t1o~,or yo~r refueling outage schedules....,,.......,.,,,.........,.
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. The report;ng and/or recordkeept~_g_..r:e.q~1-~mer;rt.s. cgnt~11')ed~ t~ ~his le~~\\f:er:
affect fewer than te.n respond_en_~;, ~h~~,fq~, QMB,cle~r~~~~ ~s _not required und~r P.L. 96... 511 *...._.,.,.
Sincerely.
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Do'ffienic B. Vassallo, Chief
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Operating Reactors Branch #2 01 vision of Ucens 1ng
Enclosure:
Request for Additional Information cc w/enclosure:
See next page
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Mr. L. DelGeorqe cc:
Mr. Philip Steptoe Isham, Lineal n & Beale ** * *
- Counselors at Law One First National Plaza, 42nd Floor Chicago, Illinois 60603 Mr. Douglas Scott
- Plant Superintendent Dresden Nucl~ar Power Station Rural Route #1 Morris, Illinois 60450 Morris Public Library 604 Liberty Street Morris, Illinois 60451 U. S. Nuclear Regulatory Commission Resident Inspector's Office Dresden Station RR #1
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Merri s, Jl ti n.oi s 60450 j*:-....,=*~'.'-~:-7~~:.:_~-. *_.._.. **:
Mary Jc) Murr.ay; Esq.
. Assistant Attorney General'-
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Envir6nm~rit~l Control Divisitiri 188 W. Randolph Street
- Suite 2315 Chicago, Illinois 60601 John F. Wolf, Esq.
3409 Shepherd Street
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- Chevy Chase, Maryl and 20015 D~. Linda W. Little 500 Hermitage Drive Raleigh, North Carolina 27612 The Honorable Tom Corcoran U.S. House of Representatives Washington, D.C.
20515 Dr. Forrest J. Remick 305 East Hamilton Avenue State College, Pennsylvania James G. Keppler 16801..
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
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- Encl osur*e REQUEST FOR ADDITIONAL INFORMATION
. **oRESDE~LCY£lF8:RELOAD* *
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492.1 In detennining the minimum critical power-ratio (MCPR) safety limit for the Cycle 8 reload, the applicant has used the method described in XN-NF-524, "Exxon Nuclear Company Critical Power Methodology for Boiling Water Reactors."
In order to detennine the acceptability of the proposed MCPR safety limit the applicant must perfonn the following:
- 1.
Supply the data used to generate the uncertaint1es ~employed in the methodology, (i.e.' distributions, means, standard deviations, and histograms).
- 2.
Demonstrate, by discussion, that those parameters not statistically convoluted are placed at their most limiting value.
3~
.;*.... *~*7.*:.:<*~:.~*1 Demonstrate that the uncertainties in plant parameters are
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treated with at least* a 95% probability at a---95,; confidence
. level in accordance with-Acceptance Criteria~ 1.0 ~f Standard Review Plan Section 4.4.
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- 4.
Perfonn a goodness-of-fit analysis for the. fitting of the Pearson curve in order to insure that the number of Monte Carlo trials used in establishing the safety limit MCPR are sufficient.
492.2 Additional plant specific infonnatio~ is required on the ACPR calcul-
. ations perfonned using the methodology describe,in XN-NF-81-22.,
"Generic Statistical Uncertainty Analysis t1ethodology~u Perfonn the*
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fol _lowing :
- 1.
Supply the variances and distributions of the predictor variables used in the response surface fitting and sufficient data to identify the mean and statistical variation of each predictor variable.
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Supply the experimental design used in the construction of the response surface. If it is not one of the three designs referenced in XN-NF-81-22, also provide justification on why this new design is acceptable.
- 3.
Demonstrate, by discussion*, that all plant parameters not treated statistically and any predi~tor variable which was eliminated from the response surface fitting are placed at their conservative values.
- 4.
Supply a goodness-of-fit analysis, the results 'of the analysis, and the criterion for acceptability for the constructed response surface uncertainties in the value of predictor. *
- 5.
Demonstrate that the variables, response variable, and talculational methods are treated with at least a 95% pro.bab11 ity at *a gs%
confidence level in accordance with Acceptance Criterion 1.0 of the Standard Review Plan Section 4.4.
- 6.
If the quadratic fit of the response surface is not adequate,*
demonstrate that the estimates of the errors in the first four moments of the probability distribution are small~
- 7.
Provide goodness-of-fit analysis in *the pro~ability distributibn.
- 492.3 With regard to Table 5.4 of XN-NF-81-76, suppl_y the following:.
- 1.
Were the ACPRs for all three fuel types (XN-1, 8x8R, 8x8) calculated from separate response surface.s?. If so, provide the infonnation requested in 492.2 for each surface. If one surface was used for all of the fuel types, demonstrate that the one surface is applicable to all fuel types.
- 2.
Define what is Meant by "typic~l value for 8x8R and P8x8R fuel types".
492.4 Differences exist between the upper tie plat~ loss coefficients an6
- the functions which represent the spacer loss coeff1cients.
Provide a discussion on how the above discrepancies effect the thennal margin calculations and normal operation of the reactor.
Also~ supply the acceptance criterion used by ENC to detennine hydraulic compatability of different fuel types.