ML20041G284
| ML20041G284 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/26/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| References | |
| IEB-80-04, IEB-80-4, TAC-46851, TAC-46852, NUDOCS 8203190508 | |
| Download: ML20041G284 (7) | |
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FEB 2 01982 DISTRIBUU0ft:
h() db CITo'cket Filed f1RC PDR L PDR Docket flos. 50-266 f1 SIC g
and 50-301 TERA ff Nd(\\
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OELD ql Mr. Sol Burstein I&E-3 z-5 o
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Wisconsin Electric Power Cocpany JHeltemes 47.i;g,g '/
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fillwaukee, Wisconsin 53201 PMKreutzer-3 g
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Dear Mr. Burstein:
Gray File WBulter In conducting our review of your reskonggaEB IE Dulletin 80-04, " Analysis of a PWR fiain Steam Line Break With Continued Feedwater Addition", at Point Ocach fluclear Plant. Units flo.1 and 2, we have determined that we will need the additional information identified in the enclosure to continue the review.
In order for us to raaintain our review schedule, your response is requested within 45 days of your receipt of this letter. The reporting and/or redordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OM3 clearance is not required under P.L.96-511.
Please contact us if you have any questions concerning this requsst.
Sincerely, Original W. ut by Robert A. Clark Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page TAC #: 46851, 46852
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FEB 26 1gc2 Docket flos. 50-266 and 50-301 J
Mr. Sol Burstein Executive Vice President Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, Wisconsin 53201
Dear Mr. Burstein:
In conducting our review of.ycur response to IE Bulletin 80-04, " Analysis of a PWR Main Steam Line Break With Continued Feedwater Addition", at Point Beach fluclear Plant, Units flo.1 and 2, we have determined that we will need the additicnal information identified in the enclosure to centinue the review.
In crder for us to maintain cur review schedule, your response is requested within 45 days of your receipt of this letter. The repcrting and/cr recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
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Please contact us if you have any questicns concerning this request.
Sincerely, Cr jc\\
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Rcbert A. Clark, Chief Operating Reactors Branch #3 Divisicn of Licensing
Enclosure:
Recuest for Additional Infcrmation cc w/ enclosure:
See next page m.
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o' Wisconsin Electric Power Company CC:
Mr. Bruce Churchill, Esquire Mr. William Guldemond Shaw, Pittman, Potts and Trowbridge USNRC Resident Inspectors Office 1800 M Street, N. W.
6612 Nuclear Road Washington, D. C.
20036 Two Rivers, Wisconsin 54241 Joseph Mann Library 1516 Sixteenth Street Two Rivers, Wisconsin 54241 Mr. Glenn A. Reed, Manager Nuclear Operations Wisconsin Electric Power Company Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, Wisconsin 54241 Mr. Gordon Blaha Town Chai'rman Town of Two Creeks Route 3 Two Rivers, Wisconsin 54241 Ms. Kathleen M. Falk General Counsel Wisconsin's Environmental Decade 114 N. Carroll Street Madison, Wisconsin 53703 U. S. Environmental Protection Agency Federal Activities Branch Region V Office ATTN:
Regional Radiation Representative 230 S. Dearborn Street Chicago, Illinois 60504 I
Chai rman Public Service Connission of Wisconsin Hills Farms State Office Building Madison, Wisconsin 53702 Regional Administrator Nuclear Regulatcry Commission, Regien III Office of Inspection and Enforcement 799 Roosevelt Rcad Glen Ellyn, Illinoir' 50137 w
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REQUEST FOR ADDITIONAL INFORMATION PWR MAIN STEAM LINE BREAK WITH CONTINUED PEEDWATER ADDITION WISCONSIN ELECTRIC POWER COMPAtiY POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 NRC DOCKET NO. 50-266, 50-301 NRC TAC NO. 46851, 46852 A
Id. l ranklin Research Center F
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e-s BACKGROUND Evaluation of the information contained in the April 25, 1980 letter (1) from Wisconsin Electric Power Co. (WE) to the U.S. Nuclear Regulatory Co= mission (NRC) relating to IE Bulletin 80-04, " Analysis of a PWR Main Steam s
Line Break with Continued Feedwater Addition," revealed an item of concern.
Additional information relating to' this concern is needed before a final evaluation can be made regarding the potential for exceeding containment design pressure.
This concern and the additional informatien needed to resolve this concern' a:e identified in this Request for' Additional Information.
Supplemental information new held by.FRC relat'ing to this matter is noted in the bibliography included in this request.
ITIM CCNCERN IE Sulletin 80-04 directs the Licensee to review containment pressure response to a main steam line break (MSL3) accident to determine the impact of runcut flew from the auxiliary feed. water (AFR) system and other ene:gy sources.
WE's :espense concerning the MSL3 analysis for the ?cint Beach Nuclear Plant, Units 1 and 2, stated that the analyses for steam line br'eak did not include a detailed blewdown and contain=ent response analysis.
Ecwever, the centsin. ment pressu:e response was ccepa:ed to a less-ef-coolant accident (LCCA). To deter-
=ine the centainment response to a MSL3, an instantaneous release of 165,000 lb 6
and 140 x 10 STU was conse:vatively assumed for the respective mass and energy :elease to the containment.
Assu=ption cf a continued AFW flew cf 400 6
gp= predicted a centinued energy release rate of 3.9 x 10 STU/=in, allowing l
a 7.5-minute =argin before the LCCA assumptiens were exceeded, without taking credit for echtainment spray and cooling syst'ms.
e WI's response is not sufficient to allow FRC to cceplete.the evaluation of the potential for exceeding contain=ent design pressure.
The values used for the enthalpy released instantaneously and that released by the continued addi-tion of feedwater are inconsistent.
The instantaneously released enthalpy is E FrankJin Research Center a es w s. rry ma,.
O approximately 850 BTU /lbm, whereas the continued feedwater blowdown enthalpy,
is approximately 1170 BTU /lbm.
Additionally, the analysis alludes to the requirement for operator action but does not state at what time operator action is required.
REQUEST
'Please provide the following information concerning your analysis of containment pressure response to a MSLB with continued feedwater addition:
1.
The assumptions used and a justification of the quantities determined for the followings a.
The instantaneous energy and mass release to the containnent for the MSL3 analysis.
b.
The energy release to the containment from the continued addition of feedwater.
2.
If you feel that you cannot provide adequate justification for using the above =entioned assu=ptions and the original assu=ptions need to be reconsidered, reevaluate the potential for exceeding containment design pressure using the new assu=ptions.
If you wish to take credit for operator action either using your original assu=ptions or new assu=ptions (and subsequent reanalysis), please answer the following questions:
3.
Your submittal of April 25, 1980 alludes to operator action but does not state what actions are required to be :aken and at what time the action is required. Provide this information and the justification for the time assu=ed for opera:or actions.
4 If yo6r analyses requires operator action to =itigate :he containment pressure consequences of th MSL3, provide the time when containment design pressure will be exceeded, if no operator action is take.n.
Provide also the magnitude of the peak pressure and the time at which the peak occurs.
A dSnklin Research Center 4 D= on of N benaan mennae
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4 REFERENCE i
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C. W.
Fay (WE)
Letter to J. G. Keppler (NRC)
April 25, 1980 J
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SIBIDGRAPHY 1.
Point Beach Nuclear Plant Unit 1 l
Final Safety Analysis Report Sections 14.2.5 and 14.3.4 I
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