ML20031E485
| ML20031E485 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 09/22/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Jackie Cook CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8110150610 | |
| Download: ML20031E485 (2) | |
Text
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SEP 22 M DISTRIBUTION Docket bec: TERA /NSIC/ TIC LB#4 Reading NRC PDR EAdensam Local PDR DHood ACRS(16)
Docket Nos. 50-329 MDuncan and 50-330 DGEisenhut/RPurple w/o encl:
SHanauer W. Jensen RVollmer G. Mazetis TMurley P. Check Mr. J. W. Cook RMattson R. Hernan Vice President RHartfield,MPA W. Brooks OELD L. Phillips Consumers Power Company 1945 West Parnall Road OI&E(3)
Jackson, Michigan 49201 i
Dear Hr. Cook:
Subject:
Transmittal of Supplement to Preliminary SER Draft Section 15 Midland Plant, Units 1 and 2 Enclosed for your review and cossnent is a supplement to preliminary draft Section 15 of the NRC staff's Safety Evaluation Report for Midland Plant, Units 1 and 2 as forwarded August 17, 1981. This supplement consists of an additional open item concerning core peaking factors, fuel damage, core power and pressure for the Steam Line Break Analysis.
A principal objective of this transmittal is to provide for timely identification and resolution of any additional analysis, missing information, clarifications or other work necessary to resolve outstanding issues. Please contact the staff's Project Manager regarding the need for any meetings and telephone conferences to this end.
Your comments, including schedules for completion of any further analyses or l
other work associated with msolution of open items, are requested within two weeks of this letter.
l Sincerely, orisiaal danad kr nobat 1. Tedesa i
l l
Robert L. Tedesco, Assistant Director for Licensing l.
Division of Licensing
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CHAPTER 15 ADDITIONAL OPEN ITEM l',2in Steam Line Break (Section 15.1.5)
Figure 15.1-9 of the' FSAR indicates that core thermal powers of 25 to 30 percent are reached in the event of a 2.0 square foot main steam line break at approximately 80 seconds following a reactor trip wher, the reactor system pressure is about 700 psia.
If a stuck rod were present, large local peaking factors may occur and DNB may occur in local regions.
Provide the core peaking factors for this condition, percent of rods in DNS and core power and pressure at time of ninimum DNBR.
Justify that this case is bounded by the doubla ended break case which is stated t, produce the maximum number of rods in DN3.
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