ML18046B353
| ML18046B353 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/08/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Vandewalle D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| IEB-80-04, IEB-80-4, LSO5-82-03-052, LSO5-82-3-52, NUDOCS 8203120225 | |
| Download: ML18046B353 (3) | |
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UNITED STAT(b NUCLEAR REGULATORY COMMISSION WASHINGTON,o: c*. 20555 March. 8,. 1982_
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'.;-_,,,.t-DTSTRIBUfION
. Docket NRC PDR Lcoal PDR ORB Reading NSIC -
Docket No. 50-255 LS05-82-03-052 DCrutchfi el d.
HSmith TWambach Mr. David VandeWalle Nuclear Licensing Administrator Consumers Power Company 1945. West Parnall Road Jackson, Michigan 49201 Dea~ Mr. Vandewalle:
OELD OI&E ACRS (10)
SEPB
- PHearn JDonohew
SUBJECT:
LICENSEE RESPONSE TO BULLETIN 80-04 FOR. THE PALISADES PLANT
~ANALYSIS OF A PWR MAIN STEAM LINE BREAK WITH CONTINUED FEEDWATER ADDITION" Our contractor, Franklin Research Center (FRC), is conducting a review of the responses to Bull~tin 80-04.
They have reviewed your r~spbnse and have a need *for more information to complete their review.
The enclosure to this letter contains their requests for additional infor-mation. *We ask that you respond within 45 days of your receipt of this 1 etter.
Since this request is being sent only to Consumers Power Company and relates to an issue specific to Palisades, no clearanc~ from the Office of Management and Budget (OMB) is required.
Enclosure:
Request* for Add it i ona 1 Information*
- cc*w/enclosure:
See-enxt page
- Si nee re 1 y, L
711., ~J!"A§_,j~.f~
Dennis M. Crutchfield Operati~g Reactors B anch #5 Division of Licensing USGPO: 1981-335-960
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Mr.* David J. VandeWalle cc M. 1. Miller, Esquire
-. Isham, Lincoln & Beale
-*Suite 4200 -
One First National Plaza Chicago, Illinois 60670 Mr. Paul A. Per.ry, Secretary
- Consumers Power Company 212 West Michigan Avehue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Av.enue Jackson, Michigan 49201
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CHERRY & FLYNN Suite 3700 Three First National Plaza Chicago, Illinois 60602 Ms. Mary P. Sinclair
- Great Lakes Energy A 11 i ance 5711 Summerset Ori ve Midland, Michigan 48640 Ka 1 amazoo Public Li bra ry 315 South Rose Street Kalamazoo, Michigan 49006 1ownship Supervisor Cove rt Towns hi Route 1, Box 1 0 Van Buren CouMty, Michig~n 49043 Office of the Goverpor (2)
Room 1 - Capitol Building
. Lansing, Michtgan 48913 William J. Scanlon, Esquire 2034 Pauline Boulevard
. Ann ~rbor~ Michiga~. 48103 Palisades Plant ATTN:. Mr. Robert Montross P 1 ant Man age r Covert, Michigan 49043 March 8, 1982 U. s.* Envi ronmerital Protection Agency Federal Activities Branch Region V Office ATTN:
Regional Radiation Representative 230 South Dearborn Street
- Chicag6, Illin6is 60604 Charles Bechhoefer, *Esq.*, Chairman Atomic Safety and Licensing Board Pane 1.
U. S. Nuclear Regulatory Commission W a s h i n gt on, D
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2 0 5 5 5 Dr. George C. Anderson Department of Ocea~ography University of Washington Seattle, Washington 98195 Dr. M. Stanley Livingston 1005 Calle Largo Santa Fe, New Mexico
- 87501 Resident Inspector c/o U. S. NRC Palisades Plant Route 2, P. O. Box 155 Covert, Michig~n 49043 James G. Keppler, Regional Administrator Nuclear Regulatory Comm1ssion, Regi'on III Office of Inspection and Enforcement 799 Roosevelt Road Glen Ellyn, Illinois 60137
REQUEST FOR ADDITIONAL INFORMATION PWR MAIN STEAM LINE BREAK WITH CONTINUED FEEDWATER ADDITION PALISADES PLANT.
DOCKET NO: 50-255 Evaluation of the information contained i~ the May 9, 1980 letter from Consumers Power Company (CPC) to the u~ S. Nuclear Regulatory Commission (NRC) relating to IE "Bulletin 80-04, "Analysis of a PWR Main Steani Line Break with Continued Feedwater Addition, 11 revealed
. several items of concern. Additional information relating to t.hese concetns is needed before a final evaluation can be made regarding the potential for exceeding containment design pressure or worsening of reactor return-to-power response.
CONCERNS 1E Bulletin 80-04 directs the Licensee to ~eview tont~inment pressure response.to a main steam line break (MSLB) accident to determine the impact of runout flow from the auxiliary feedwater (AFl~) system and other energy sources.
CPC 1s response concerning the MSLB analy~is for the Palisades Nuclear Power Plant.indicated that main feedwater (Mm) flow ramped down from full flow to zero flow at 60 seconds post-reactor trip.
CPC 1 s response is not sufficient to allow FRC to complete the evaluation of the potential for exceeding containment design press~re. It is not apparent that the analysis considered a single active failure of the MFW system and its effect on increasing the previously assumed MFW flow rate.
IE Bulle~in 80-04 directs the licensee to review the reactivity increase which results from a MSLB inside or out~ide containment.
Th~ licensee's analysis of the reactivity response to a MSLB with con-
- tinued feedwater addition indicated that in each full power* case MFW flow was assum~d to be reduced from full flow to 5% full flow over the 60 seconds immediately following a reactor trip. This analysis also did not address the possibility that a single active failure of a MFW component might lead to greater than the assumed flow.
- 1.
An evaluation of the potenttal for single active failur~ in the.MFW system which cpuld cause the ~reatest feedwater fl.ow to.the affected.
steam generator during a MSLB accident and a determination of MFW.
flow rate to the affected generator if a single active failure were to occur, please provide response.
- 2.
If the response to request 1 results in MFW flow greater t~an that in previously accepted analyses, provide a quantitative analysis of the containment pressure respon.se* and core reactivity response to*
a MSLB using the feedwat~r runout flow identified in request No. 1.
Provide justification for the*assumptions made in the ~nalysis.
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