ML20024B223
| ML20024B223 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/31/1974 |
| From: | Ward E BABCOCK & WILCOX CO. |
| To: | Heward R GENERAL PUBLIC UTILITIES CORP. |
| References | |
| TASK-*, TASK-GB GPU-2491, NUDOCS 8307070369 | |
| Download: ML20024B223 (4) | |
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July 31, 19%
AUG 7 1974 Mr. R. W. Eevard, Project Ma:ager l
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gg Parsippany, H. J.
0705h e,<_
Subject:
Sree Mile Island Nuclear Statics, Unit #1 ECCS Analysis 3&W Reference, USS-5
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Dear Mr. Eevard:
On January k,197k the AIC issued the Final Acceptance Criteria (FAC) for 2005 evaluation en the for= of revisions to 10 CF2 50.k6.
Sese revisicas require that for plants which have operating licenses or which =ay receive an operating lice:se on or before Dece=ber 28,197k, an ECCS evaluatien be sub=itted to the AEC by August 5 which is perfor:ed with a =cdel that ec for=s to the require =ents of Appendix K of 10 CFR 50.
3&W vi n previde the required sub=ittal en a generic basis which vin satisfy the above require =ents for your plant.
De folleving infor=ation s"-"-ices our status and schedule with respect to
=ceting the above referenced docu=entatic for the revised ICOS evaluatien. 3&W has ce=pleted the final ec=putaticus for the analysis of a generic 177 FA plant with lowered icops. The basis for this generic anal / sis is to use li=iting values of key para =eters, such as power level and centai==ent building size, for all plants which are in this categcry. Se spectru= of breaks has been analyced and the results shov that the vorst break is a double-ended guillotice at the pu=p discharge. The peak linear heat rate which =eets the 14-iting revised criteria (peak cladding te. perature <2200?) is 18.00 kW/ft at the six foot elevation. This value is greater than the existing LCCA li=it established under the Interi= Acceptance Criteria (IAC) for ycur plant. A11cvable linear heat rates at other elevatices have also been established, and the results shev sc=e reductica i= these values below the core =idplace relative to the IAC results. Eence, sc=e further restricticas in red insertion
-d ts win be required as. a ec= sequence for your plant. These additional restricticas are only te=porary, since the LCCA li=its were developed on a generic basis. 3LW vill perfor= additic a1 analysis which will be bpsed on the para =eters specific to your plant to =ici= ice the effect of the new red insertion li=its.
Sis analysis will be perfor=ed as expe-ditiously as possi' ole and the results vi n be trans=itted to you as seca as they are available. We vi n provide you vith the sched" a '- ce=pletion of this additional analysis by August 7, 197k.
By August 5, 3&W vin have sub=itted the foneving tcpical reper:s which p cride the =ajor portion of the necessary docu=entatien fer your plant.
$387 E M'oN 8cSe9 WO26405 P
O The Babecck & Wilces Comcany / Establisnec 1867
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BabCDCk & Wi!COX Mr. R. W. Hevard, P.M.
GPU Service Corporation
Subject:
ICCS A=alysis July 31, 197h 1.
BAW-10091, "B&W's ECCS Evaluatien Model Report with Specific Applicatien to 177 FA Class Pla=ts with Iovered Loop Arrange =ent" 2.
BAW-10092, "CRA?f 2-Fortra: Progrs= for Digital Si=ulation of a Multimede Reactor Plant During Less of Coolast" 3.
3AW-10093, "REFLCOD - Descriptien of Model for Multinode Core Reficed Analysis" 4.
BAW-10094, "Babecek & Wilecx Revisiccs to THrfA 1-3, A Cc=puter Code for Nuclear Reactor Core Ther=al Analysis - IH-1kk5" 5
BAW-10095, "Babecek & Wilcox Revisicus to CCIm?T - Cc=puter Progra= for Predicting Contai---a* "-assure - Te=perature Respense to a Loss-of-Coclant Accident" Draft versic=s of each of these topicals have been reviewed b7 the AEC Staff. 3&W has provided responses to the Staff's ce==ents, = cst of which are relatively =iner in nature, and B&W believes that the acceptance of the =cdel vill be obtained with little difficulty. The current AEC schedule calls fer ec=pletion of their Safety Evaluatica Report on the =edel by the end of August 197h.
The previous referenced topical reports vill be forvarded to you as they are completed for filing with the AIC.
Attached you vill find a suggested letter which you ca: use for trans=ittal to the AEC to de=cestrate ce=pliance for your plant to the FAC. This letter =ust be filed by your ec=pany with the AIC cn or before August $.
Included in the letter are the following: 1) generic FAC LOCA li=1t curve and, 2) te=porary revision to red insertica li=its and correspending text changes for the Technical Specificaticus for your plant.
"'his revision is based on LOCA li=its as established en the basis of the revised ECCS analysis (3AW-10091).
As required by 10CFR 50.h6 (a) (2) (iv), you are required to sub=it proposed technical specifications for approval a=d i=ple=ent the =cre restrictive of the present and proposed red insertien 14-4ts prior to 12:01 AM August 5.
Yours very truly, h AC
- 2. G. Ward Senior Project Manager ECW:Fa*H CC:
T. Z. Cr4
- s, GPU Ser.-ice Corp., W/A J. c,-gergein, get 33, 31:3, y/A l
Jeff Fritzen, Met Id, Reading, W/A L. C. Rogers, 3&W, Site, W/A l
Don Grace, Met Id, Reading, W/A F. C. Heller, Philadelphia Sales, WC/A -
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RECO:cCDEO OPAF"'
August 5, 197h Mr. A. Gla=husso Deputy Director for Reacter Projects Directorate of Licensing U. S. Atoz=ic E=ergy Cc==ission Washi=gton, D. C. 205h5
Dear Mr. Gla=busso:
On January k,197h the AEC issued the Final Acceptance Criteria (FAC) for ICCS evaluation as revisicas to 10 CFR 50.h6.
In ce=pliance vith these revisions, Babcock & Jilecz has developed an evaluation =edel which r.eets the requirements of Appe= dix I of 10 CFR 50.
The description of this =cdel is contained within their non-proprietary topical report, 3rJ-10091, "B&W's ECCS Evaluatic Model Report "Jith Specific Application to 177 FA Class Plants with Lovered Loop Ar-ange:ent," which has been s=h=itted to the Directorate of Licensing (DOL) en Augst 5, 197h. In addition, 31V has provided supporting docu=entati:n for the ce=puter cedes utilized in this motiel in the folleving non-proprietary tcpical re;crts:
1.
BA3-10092, " CRAFT 2-Fortran Progrs= for Digital Si=ulatien> cf a Multinode Reacter Plant During Loss of Coolant" 2.
HAW-10093, "REFLOOD - Description of Model for Multinede Core Refleed A=alysis" 3.
BA7-1009h, "Babecek & Wilecx Revisiens to THIfAl-B, a Cc=puter Code for Nuclear Reacter Code Ther=al Analysis - IN-1kk5" h.
SAS-10095, "Babecek & Wilecx Revisicas to COUTEMPT - Cc=puter Pr:gra= for Predicting Centai==ent Pressure - Te=perature Response to a Less-of-Coolant Accident" The analysis presented in BNJ-10091 for the 3NJ 177 FA class plants with levered loop is ge=eric in nature, si=ce the plant para =eters utilized i= the analysis (such as the rated pcVer level, fuel densification and centai =ent builiing volu=e) are taken o be the = cst conservative values for all the plants of this type. 2.us,
the results centained in SNJ-10091 provide an overly conservative analysis for all plants of this type and can be applied to the E!I Unit 1 Plant. As such, we ad:pt the results cental ed in 3AW-10C91 to this plant. These results de_cnstrate cct-for=ance to the criteria of 10 CFR 50.h6 under the folleving operating =cnditices:
1.
The peak linear heat rate is less than er equal to 17.2 kW/ft at the six foot elevation.
2.
The plant is operating within the =est restrictive li=its of the present and the proposed Technical Specificatiens for the less-of-ce:lant li=its.
~hese revisions are based en the LOCA li=its as established fr = the revised ECCS analysis (FAC) (3AW-10091).
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