ML17326A237
| ML17326A237 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/01/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Dolan J INDIANA MICHIGAN POWER CO. |
| References | |
| NUDOCS 7908300589 | |
| Download: ML17326A237 (6) | |
Text
Hr. John Dolan, Vice President Indiana and Hichigan Electric Company Indiana and Hichigan Power Company
.Post Office Box 18 Bowling Green Station New York, New York 10004 Otiginal Signed BX J
AUGUST 1
1979 DISTRIBUTION Docket File 0-and 50-316 NRC PDR (2)
~) ~g
'ocal PDR l >~~s ORB1 Rdg Docket Nos. 50-315 i
and 50-316 W. Gammill T. J.
Car ter A+torney, OELD I:E (3)
A. Schwencer D. Wigginton C. Parrish J.
- Buchanan, NSIC TERA
Dear Hr. Dolan:
ACRS (16)
On November 7, 1978, in a letter to Hr. Tillinghast, we requested additional information on the containment sump tests for the D.
C.
Cook Units 1 and 2.
On Hay 31, 1979, a member of our staff toured the plant site and inspected tbe containment recirculation sump's a result of that inspection, we have amplified item 0'3 of our November 7, 1978 request for additional information.
This amplified information request is enclosed.
Within thir.ty (30) days from the receipt of this letter, please provide a schedule for the submittal of outstanding air entre'ilnment and jet impingement testing and your response to the enclosure.
'I it Sincerely,
Enclosure:
Request for Additional Information A. Schwencer, Chief Operating Reactors Branch 8 Division of Operating Reactors cc:
w/enclosure See next page j 90839oSB
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Docket Nos.
50-315 and 50-'316 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 August 1, 1979 Mr. John Dolan, Yice President Indiana and Michigan Electric Company Indiana and Michigan Power Company Post Office Box 18 Bowling Green Station New York, New York 10004
Dear Mr. Dolan:
On November 7, 1978, in a letter to Mr. Tillinghast, we requested additional
'information on the containment sump tests for the D.
C.
Cook Units
.1 and 2.
On May 31, 1979, a member of our staff toured the plant site and inspected the.containment recirculation sump.
As a result of that inspection, we have amplified item ¹3 of our November 7, 1978 request for additional information.
This amplified information request is enclosed.
Within thirty (30) days from the receipt of this letter, please provide a schedule for the submittal of outstanding air entrainment and jet impingement testing and your response to the enclosure.
Sincerely,
Enclosure:
Request for Additional Information A. Schwencer, Chief Operating Reactors Branch
¹1 Division of Operating Reactors cc:
w/enclosure See next page
Mr. John Dolan Indiana and Michigan Electric Company Indiana and Michigan Power Company 2
August 1, 1979 CC:
Mr. Robert W. Jurgensen Chief Nuclear Engineer American Electric Power Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, D..C.
20036 Citizens for a Better Environment 59 East Yan Buren Street Chicago, Illinois 60605 Maude Preston Palenske Memorial Library 500 Market Street St. Joseph, Michigan 49085 Mr.
D. Shaller, Plant Manager Donald C.
Cook Nuclear Plant P.
0.
Box 458 Bridgman, Michigan 49106 Mr. R.
Masse Donald C.
Cook Nuclear Plant P.
0.
Box 458
- Bridgman, Michi gan 49106
IlP V
RE UEST FOR ADDITIONAL INFORMATION DONALD C.
COOK NUCLEAR PLANT UNIT NOS.
1 AND 2 1.
The licensee must show that the D.
C.
Cook recirculation sump performs in an acceptable
- manner, assuming breaks in the high pressure reactor coolant system piping in the vicinity of the sump inlet.
Only mechanistic breaks of the reactor coolant system need be considered in reviewing recirculation sump performance.
The licensee is directed to the breaks identified in WCAP 8082 Figure II.D-l. It must be shown that the sump design has sufficient protection against breaks shown in the above mentioned figure.
Specifically, it must be shown that the D.
C.
Cook sump is protected from breaks in the closure weld of the crossover leg, hot and cold leg steam generator
- nozzles, and reactor coolant pump suction.
Some of these breaks are above the expected containment water level at switchover.
For these
- breaks, the potential exists for a water and steam jet being directed towards the sump inlet, causing air binding or other degradation of safety injection pump performance.
The effect of jet impinge-ment on the sump structure must also be considered.
Some of the postulated breaks may be below the expected post-LOCA water level.
For these, the licensee should confirm that flow from the breaks will not cause a forced rotation leading to the formation of vortices.
2.
The licensee wil.l provide diagrams of the containment in the vicinity of the recirculation
- sump, showing all high pressure piping, and the expected water levels at switchover.
The pipe breaks considered in question kl above should be indicated on the diagrams.