ML17317B463
| ML17317B463 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/20/1979 |
| From: | Dolan J INDIANA MICHIGAN POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 7908170464 | |
| Download: ML17317B463 (3) | |
Text
INDIANA 5 MICHIGAN POWER COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, H. Y. 10004 July 20, 1979 AEP:NRC:00234 Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 Mr. Jakes G. Keppler, Regional Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Region III Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
This letter serves to provide the information requested in IE Bulletin No. 79-13, dated June 25, 1979 which we received on June 29, 1979.
Subsequent to the identification of cracks in the 16-inch feed-water elbows adjacent to the steam generator
- nozzles, the four elbows on each Unit have been replaced.
After installation of the modified elbows, the elbow-to-nozzle and elbow-to-reduce1'elds were radiographed and found acceptable.
Details of the modified elbow/nozzle connection
- design, as well as the results of our examination of the feedwater piping inside containment, are contained in our previous submittals on this topic; AEP:NRC:00216, dated June 7, 1979 and AEP:NRC:00221, dated June 15, 1979.
Res onse to Item No.
5 (a)
The recent examinations/inspections performed at the Cook Plant on the feedwater system piping welds inside containment fulfillthe intent of Item No.
1 of IE Bulletin No. 79-13.
(b)
The procedures presently employed at the Cook Plant for "Loss of Feedwater" (including a feedwater line rupture) and "Main Steam Line Break" have been reviewed and found adequate; for their intended function.
v sos'o $ (,P @
Mr. J.
G. Keppler AEP:
- 00234 (c)
The following indications are available to aid in the identification of feedwater leaks inside containment:
1)
Increasing level in the containment sump and 2)
Increase in containment humidity Indication of the water level in the lower containment sump is provided by:
(a)
The low level alarm at 16 inches of water level, and (b)
The high level alarm at 108 inches of water level Additional indication is provided indirectly by observing the status of the two (2) lower containment sump pumps.
When the sump level increases the sump pumps automatically start.
Leakage from non-radioactive piping systems, e.g.
- System, are distinguished from primary system leaks by the lack of an increase in containment activity,.
The containment Humidity Monitor is provided to monitor and detect leakage from the reactor coolant pressure boundary (as required by Technical Specification 3/4.4.6. 1), but is equally sensitive to feedwater leaks equivalent to 0.2 to 1.0 gpm.
Item No.
6 The results of our examinations of the feedwater nozzle-to-elbow welds are contained in our AEP:NRC:00216 submittal, dated June 7, 1979.
Details of the feedwater piping design are contained in our AEP:NRC:00215 submittal, dated June 21, 1979.
Further information regarding the data collection program being implemented on Unit 2 is in our'AEP:NRC:00221 submittal, dated June 15, 1979.
The information in the above cited transmittals fulfills the reporting requirements of Item No.
6 of IE Bulletin No. 79-13.
As the information contained herein is being submitted at the request of the
- NRC, AEPSC interprets 10 CFR 170.22 as requiring that no fee accompany this transmittal.
Very truly yours, ohn E. Dolan Vice President Notary Publ c
Sworn ~ subscr ibed to before me this~ day of July, 1979 in New York County, New York
.6
'4o',ory l:u>h~ic. $lme o,';eg York Ho. 3l-464343l Qual':ed in N'.I York County <
Commission Expires March 3Q, 19k~
Hr. J.
G. Keppler AEP:NRC:00234 cc:
R.
C. Callen G. Charnoff R.
W. Jurgensen R. S. Hunter D. V. Shaller - Bridgman