ML17328A973
| ML17328A973 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/31/1990 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17328A972 | List: |
| References | |
| NUDOCS 9103280267 | |
| Download: ML17328A973 (9) | |
Text
ATTACHMENT TO AEP:NRC:1147A DONALD C.
COOK NUCLEAR PLANT CORRECTED ANNUAL OPERATING REPORT PAGES 910""~
HACK OSOOO31~
02g7 9i.03' F ~R ggO P),.IP R
3.0 STEAM GENERATOR IN-SERVICE INSPECTION 3.1 UNIT 1 INSPECTION
SUMMARY
One hundred percent of the tubes in all four steam generators of Unit 1 were bobbin coil eddy current inspected.
All tubes were tested utilizing a 0.720 inch diameter probe with the exceptions of rows 1 through 4 U-bends that would not allow a 0.720 inch probe to pass.
A 0.700 or 0.680 inch probe was used for the U-bend inspections only.
The bobbin coil test frequencies used were as follows:
400 kHz as the prime test frequency.
200 kHz and the 100 kHz as supplemental frequencies.
10 kHz as the locator frequency A total of 170 tubes were removed from service following this inspection due to the eddy current results.
Appendix A provides inspection details concerning the indications found in each tube and whether or not the tube was plugged.
3.2 UNIT 2 INSPECTION
SUMMARY
Six and one-half percent of the tubes in Unit 2
steam generators were inspected using the same method and test frequencies described for Unit 1 inspections.
All tests were conducted with a
0.720 inch diameter probe with the exception of three tubes in steam generator 23, located in Rows 1 and 2.
These three tubes were tested with a 0.700 inch probe.
No degradation or pluggable indications were found.
STEAM GENERATOR NUMBER 12 35 44 35 44 45 44 45 44 12 46 23 47 38 47 43 47 11 48 14 48 13 51 18 52 34 54 37 54 3
55 32%
25%
AV1 +
0 IN AV2 +
0 IN NO NO 144 144 2SPC
+
0 IN NO 1SPC
+
0 IN NO DI TEH + 17.8 IN YES DX 1SPH
+
0 IN NO DI 2SPH
+ 0 IN NO 194 AV1 +
0 IN NO DI 2SPH
+
0 IN NO DRI TEH + 2.5 XN YES DI TEH + 21.1 IN YES DI 1SPH
+
0 IN NO 264 AV4 +
0 IN NO 394 AV4 +
0 IN NO DI 1SPH
+
0 IN NO 36 55 41%
AVl +
0 IN YES 19 57 43 60 23 61 43 61 44 62 42 63 42 63 DI 1SPH
+
0 IN NO 2 1+o 1SPC
+
0 IN NO DI 1SPH
+
0 IN NO DI 2SPH
+
0 IN NO 23%
2SPC
+
0 IN NO 27%'44'V3
+ 0 IN AV4 +
0 IN NO NO 42 64 144 1SPC
+
0 IN NO 18 65 DI 1SPH +
0 IN NO 42 65 174 AV1 +
0 IN NO 41 66 DI 2SPC
+
0 IN NO ROW COL INDIC LOCATION PLUGGED 27 71 DI TEH + 20.6 IN YES 38 72 38 72 244 28%
AV3 +
0 IN AV4 +
0 IN NO NO 36 74 37 74 37 74 21 76 37 76 37 76 35 77 36 77 37 77 28 78 33 78 34 78 31 79 31 79 29 82 30 82 15%
1SPC
+ 0 XN DI DI 4SPH
+ 0 IN 1SPC
+ 0 IN DI 1SPH
+ 0 IN 154 DI 2SPC
+
0 IN 1SPC
+
0 IN 274 1SPC
+
0 IN 334 334 2SPC
+
0 IN 1SPC
+
0 IN DI 1SPH
+ 0 IN 22%'SPC
+
0 IN 15%'SPC
+
0 IN 28>
114 2SPC
+ 0 IN 1SPC
+
0 IN 274'SPC
+
0 IN 254 2SPC
+,"0 IN NO I
NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO 15 86'I TEH + 20. 6 IN YES 23 86 23 86 24 86 7
89 16 89
'9 89 13 90 35%
14%'SPC
+ 0 IN 1SPC
+
0 IN 454 2SPC
+
0 IN DI 2SPH
+
0 IN DI 2SPH
+
0 IN DI 1SPC
+
0 IN 104 1SPC
+
0 IN NO NO YES NO NO NO NO 6
91 304 1SPC
+
0 IN NO ROW COL INDIC LOCATION PLUGGED A-6
STEAM GENERATOR NUMBER 14 ROW COL INDIC LOCATION PLUGGED ROW COL INDZC LOCAT10N PLUGGED 8
30 DI TEH + 20.9 IN YES 44 39 374 4SPC
+
0 IN NO NO 34 30 37 30 42 30 5
31 41 31 DI TEH + 20.7 IN YES DI TEH + 20.5 IN YES 23%
1SPC
+
0 IN DI 2SPH
+
0 IN 134 1SPC
+
0 IN NO NO NO 32 30 DI 1SPH
+
0 IN 42 40 29 41 38 41 42 41 45 41 DI DI 2SPH
+ 0 IN 1SPH
+
0 IN
'O DI 1SPH
+
0 IN NO DI 1SPH
+
0 IN NO 194 2SPC
+ 0 IN NO NO 46 41 164 2SPC
+ 0 IN 32 32 DI 42 32 38+o 1SPH
+
0 IN 1SPC '+
0 IN NO NO 21 43 DI 1SPH
+
0 IN NO NO 44 43 DI 2SPC
+
0 IN 12 33 29+o 2SPH
+
0 IN NO 46 43 244 2SPC
+ 0 IN NO 38 33 DI TEH + '20.4 IN YES
, 30 34 DI 1SPH
+ O'N 44 34 274 1SPC
+
0 IN NO NO 17 35 32+o TSH +
~ 5 IN YES 41 45 23+o 41 45 18>o AV3 +
0 IN AV4 +
0 IN NO NO 16 46 DI TSH + 1.1 IN YES 10,45 DI 1SPH
+
0 IN NO 17 45 DI TSH +.5 IN YES 33 35 DI 1SPH
+
44 35 194'SFC
+
0 IN 0 IN 44 36 26+o 1SPC
+
0 IN 45 36 164 1SPC
+
0 IN 17 37 DI 1SPH
+
0 IN 29 37 DI 1SPH
+
0 IN 38 37 DI 2SPH
+
0 IN NO NO NO NO NO NO NO 22 46'I TEH + 21. 2 IN 33 46 24%
33 46 344 33 46 26+o AV2 +
0 IN AV3 +
0 IN AV4 +
0 IN YES NO NO NO 42 46 DI TEH + 20.8 IN YES 46 46 19%
2SPH
+
0 IN NO 38 48 18'SH
+ 42
~ 8 IN NO 44 37 39 2SPC
+ 0 IN NO 32 49 DI 2SPH
+
0 IN NO 45.
37 14'SPC
+
0 IN 45 37 16'SPC
+
0 IN 29 39 DI 1SPH
+
0 IN 38 39 DI 1SPH
+
0 IN NO NO NO NO 46 49 DI 8
50 DRI 1SPH
+
0 IN NO TEH + 2.4 IN YES 12 50 DI 1SPH
+
0 IN NO 46 50 DI 1SPH
+
0 IN NO A-13
STEAM GENERATOR NUMBER 14 ROW COL INDIC LOCATION PLUGGED ROW COL INDIC LOCATION PLUGGED 23'1 45 51 18 52 18 54 DI 1SPH +
0 IN 134 2SPC
+
0 IN NO NO DRI TEH + 2.1 IN YES DRI TEH + 2.2 IN YES 44 55 DI 2SPH
+
0 IN NO 30 57 DI 1SPH
+
0 IN 30 57 DI 3SPH
+
0 IN 22 60 DI 1SPH
+
0 IN 44 60 14%
3SPC
+
0 IN 12 61 DI 1SPH
+
0 IN 17 61 DI 1SPH
+
0 IN 20 61 DI 1SPH
+
0 IN
'30 61 DI 1SPH
+
0 IN 43 61 31%
1SPC
+
0 IN NO NO NO NO NO NO NO NO NO 13 62 DI 1SPH
+
0 IN NO 35 62 DI 1SPH
+
0 IN NO 19 63 2 2~o AV2 +
0 IN NO 19 63 194 AV3 +
0 IN NO 19 63 11%
AV4 +
0 IN 'O 26 69 26 69 18 70 31 70 30 73 33 73 39 73 4
74 5
74 18 74 33 74 33 74 13 75 33 75 35 75 36 75 4
76 17 76 18 76 154 16>o AV1 +
0 IN AV2 +
0 IN NO NO DI 2SPH
+ 0 IN NO DI 1SPH
+
0 IN NO DI TEH + 20.6 IN YES DI
.,DI 1SPH
+ 0 IN 2SPH
+ 0 IN NO NO DI 1SPH
+
0 IN DI 2SPH
+
0 IN 24+o 2SPC
+
0 IN NO NO NO 38%
2SPC
+
0 IN NO DI 2SPH
+
0 IN NO DI TEH + 20.9 IN YES DI TEH + 20.9 IN YES DI 1SPH
+
0 IN NO DI 1SPH
+
0 IN NO DI 1SPH
+
0 IN NO DI 1SPH
+
0 IN
~
NO 164 2SPC
+
0 IN NO 6
65 DI 1SPH+
0 IN 17 65 DI 1SPH
+
0 IN NO NO 19 76 DI TEH + 20.6 IN YES 41 65 344 2SPC
+
0 IN NO 31 76 DI
'SPH
+
0 IN NO 19 66 15'V1 +
0 IN NO 19 66 224 AV2 +
0 IN NO 19 66 244 AV3 +
0 IN NO 25 66 DI 1SPH
+
0 IN NO 34 67 DI TEH + 20.7 IN YES 33 76 DI 1SPH
+
0 IN NO 36 76 21%
1SPC
+
0 IN NO 23
. 77 DI TEH + 20.8 IN YES 33 77 544 2SPC
+
0 IN YES 23 78 DI 3SPH
+
0 IN NO A-14 t
Docket Nos.
50-315 and 50-316 MAR 2 i mg~
Mr. Milton P. Alexich, Vice President Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Dear Mr. Alexich:
SUBJECT:
OPERATIONAL EVENTS WHILE SHUTDOWN DISTRIBUTION:
NRC 5 L
1 P
lt PD III-1 r/f ~~r JZwol inski PShuttl eworth TColburn ACRS(10)
EJordan PDIII-I Gray OGC The NRC has just issued Information Notice 91-22, "Four Plant Outage Events Involving Loss of AC Power or Coolant Spills," which addresses recent events that occurred during shutdown operations.
The chief purpose of this information notice is to notify each licensee that the high rate of precursor events to loss of decay heat removal during shutdown is a source of concern to the NRC.
All of the events discussed in this information notice occurred during a one-week period in March 1991.
Because of the potential for loss of a critical safety function in these and similar
- events, I believe a high level of management attention is required in the planning, coordination, and execution of shutdown operations.
While this information notice does not require specific licensee action or
- response, I urge you to give this important matter your personal attention.
Sincerely, Ori-ginal signed by, Thomas E. ),lurley Thomas E. Murley, Director Office of Nuclear Reactor Regulation cc:
See next page OFC
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- PD PDIII-NAME:PShuttleworth/$ g:
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O UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 MAR g 1 ]gg)
Docket Nos. 50-315 and 50-316 Mr. Milton P. Alexich, Vice President Indiana Michigan Power Company c/o American Electr ic Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Dear Mr. Alexich:
SUBJECT:
OPERATIONAL EVENTS WHILE SHUTDOWN The HRC has just issued Information Notice 91-22, "Four Plant Outage Events Involving Loss of AC Power or Coolant Spills," which addresses recent events that occurred during shutdown operations.
The chief purpose of this information notice is to notify each licensee that the high rate of precursor events to loss of decay heat removal during shutdown is a source of concern to the NRC.
All of the events discussed in this information notice occurred during a one-week period in March 1991.
Because of the potential for loss of a critical safety function in these and similar
- events, I believe a high level of management attention is required in the planning, coordination, and execution of shutdown operations.
While this information notice does not require specific licensee action or
- response, I urge you to give this important matter your personal attention.
Sincerely, Thomas E. Murley, Office of Nucl ear Reactor Regul ati on cc:
See next page
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