ML17325A326
| ML17325A326 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/06/1987 |
| From: | Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8710160130 | |
| Download: ML17325A326 (3) | |
Text
REGULATOR INFORMATION DISTRIBUTION-I STEM
<R1DS)
ACCESSION NBR: 87f0160f30 DQC. DATE: 87/f0/06 NOTARIZED: NO, DOCKET FAG IL: 50-3i 5 Donald C.
Cook Nuc lear Poeer P lant. Unit ii Indiana 0<
05000315 50-3f 6 Dona 1 d C.
Coo k Nuc 1 ear Power Plant'nit 2.
~4c 050003 f6 AUTH. NAME AUTHOR AFFILIATION SMITHS'. G.
Indiana Michiaan Poujer Co.
REC IP. NAME RECIPIENT AFFILIATION DAVISIA. B.
, Region 3I Office of Director
SUBJECT:
Informs of number of steam generator tubes plugged as result of eddy curremt exam activities performed during Sept f987 surveillance outage. Total number of.tubes.
examined in each steam generator listed.
DISTRIBUTION, CODE:
IEOID COPIES RECEIVED: LTR t
ENCL Q SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:
RECIPIENT ID CODE/NAME PD3-3 PD INTERNAL: AEOD NRR MDRISSFAUT D NRR/DREP/EPB NRR/DRIS DIR OE LIEBERMANIJ REC RQ FILF Of" EXTERNAL:
LPDR NSIC CQP IES LTTR ENCL RECIPIENT ID CODE/NAME WIGGINQTONi D DEDRO NRR/DOEA DIR NRR/DREP/RPB NRR/PMAS/ILRB OGC/HDSi RES DEPY GI NRC PDR COPIES LTTR ENCL fi 2i f
f O
TOTAL NUMBER OF CQP IES REQUIRED:
LTTR 20 ENCL
Indiana Michigan Power Company Cook Nuclear Plant P.O. Sox 458 Sridgman Ml 49106 616 465 5901 INOIANA NICHIGAN POWER PRICRITY RGVTIHG October 6,'987 yes I 0
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Mr. A.B. Davis United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL, 60137
Dear Mr. Davis:
Pursuant to the requirements of D.C. Cook Plant Technical Specification 4.4.5.5(a),
this letter is to inform you of the number of steam generator tubes plugged as a result of eddy current examination activities performed during the September 1987 Unit 2 surveillance outage.
Inspection of Unit 2 steam generators began on September 10,
- 1987, was completed on September 25, 1987 and included 100 percent of all tubes previously not plugged.
Each tube was inspected on the hot leg only, from the tube end to just about the seventh tube support plate.
The total number of tubes examined in each steam generator. included 3,229 in S/G 21, 3,144 in S/G 22, 3,140 in S/G 23, and 3,166 in S/G 24.
P Conservative steam generator tube plugging criteria, similar to that utilized during the previous inspection of Unit 2 steam generators, were implemented as follows:
In the hot leg tubesheet crevice and tubesheet surface regions (up to approximately 6 inches) all clear indications or other signals representing possible tube wall degradation, regardless of voltage or phase
- angle, were plugged.
At hot leg support plate intersections clear indications meeting a threshold voltage of 1.75 volts and having indicated through wall penetrations of h
40 percent were considered pluggable.
In
- addition, some indications not meeting the threshold voltage were also plugged as an additional precaution based on the recommendation of the data interpreter.
87ipibp130 85pppgi5 7ippb
@DR ADDCK P PDP P
Mr. A.B. Davis October 5, 1987 Page 2
0 Applying the conservative evaluation criteria resulted in plugging a total of 78 tubes.
The number of tubes plugged per steam generator was 14 tubes in S/G 21, 17 tubes in S/G 22, 17 tubes in S/G 23, and 30 tubes in S/G 24.-
Respectfully, W.G. Smith, Jr.
Plant Manager
/cbm CC A.A. Blind INFO L.S. Gibson INFO J.E.
Rutkowski INFO M.P. Alexich INFO J.G. Feinstein - INFO S.H. Steinhart INFO M. Marrocco/D.R. Hafer/J.R.
Jensen
-INFO R.F. Kroeger INFO J.R.
Sampson INFO NRC Resident Inspectors INFO R.T. Rickman INFO File