ML17317A878
| ML17317A878 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/09/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Tillinghast J INDIANA MICHIGAN POWER CO. |
| References | |
| NUDOCS 7901220044 | |
| Download: ML17317A878 (6) | |
Text
January-9, 1979 Docket No. 50-316 Mr. John.Tillinghast, Vice President Indiana and Michigan Electric Company In'diana and Michigan Power Company-Post Office Box 18-Bowling Green Station New York, New York 10004
Dear Mr. Tillinghast:
DISTRIBUTION Docket 50-316 NRC PDR Local PDR NRR Reading ORB RF BGrimes VStello DEisenhut ASchwencer MMlynczak OELD CParrish TERA go-3/p lie have reviewed the information you submitted by.
letter dated September 20, 1978, regarding the containment temperature and pressure response to a postulated steamline accordance with condition 2.C(3)(g) of Facility Operating l
License No.
DPR-74 for the Donald C.
Cook Nuclear. Plant, I'nit 2.
As a result of our review of your submittal, we have developed the enclosed request for additional infor-mation.
Your response is requested by-February 2, 1979.
t Sincerely,
,."@nial sfgne 4
A. Schwencer, Chief Operating Reactors Branch 81 Division of Operati ng Reactors k3 veoxzscn'l'f 11 Enclsoure:
Request for Additional Information cc:
M/encl osure break inside containment.
This information was submitted in osslcd rs'UIINANd&
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Indian 5 Michigan Electric Company - 2 Indian 5 Michigan Power Company January 9,
1979 CC:
Mr. Robert W. Jurgensen Chief Nuclear Engineer Americpn Electric Power Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire Shaw, Pittman Potts E Trowbridge 1800 M Street, NW Washington, D.C.
20036 David Dinsmore Comey Executive Director Citizens for a Better Environment 59 East Van Buren Street Chicago, Illinois 60605 Maude Reston Palenske Memorial Library 500 Market Street St. Joseph, Michigan 49085 Donald C.
Cook Nuclear Plant ATTN:
Mr.
D. Shaller Plant Manager P.
- 0. Box 458 Bridgman, Michigan 49106 Kenneth R. Baker 2874 Robin Hood Drive Stevensville, Michigan 49127
ENCLOSURE ion k Nuclear Plant Unit 2 022. 17
~e require additional information regarding your analyses of the containment temperature response to postulated main steam line break(s) which you provided in your response to NRC ~equest 022.9, Specifically, we will require the following information to complete our review of the containment response to postulated ruptures of the main steam line inside containment.
For the worst split break (i.e.,
305 power level with assumed failure of the auxiliary feedwater runout protection system),
provide the results of containment response analyses using the LOTIC-3 code f'r a spectrum of break sizes ranging in size up to the 0.942 ft break previously analyzed.
The spectrum of breaks analyzed should include the largest split break which would not result in automatic initiation of the containment spray system and the largest sp1it break which would not result in automatic initiation of the containment return air fan(s).
For each break analyzed provide:
1) a figure similar to figure 022,9-2 (Appendix g) showing upper and lower compartment temperature as a function of time; 2) a figure showing containment pressure as a function of time; 3) a table similar to Table 022.9-2 (Appendix g) identifying the mass and energy release rate data used in the containment analyses; and
(g
4) dentification of any actions assumed to be performed by a control room operator ur ng e c d i the course of the accident and the time at which operator actions are assum assumed to occur. including justification for the assumed operator actions.