IR 05000320/1977046
| ML19220B278 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/21/1977 |
| From: | Haynes R, Narrow L, Walton G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B272 | List: |
| References | |
| 50-320-77-46, NUDOCS 7904250579 | |
| Download: ML19220B278 (3) | |
Text
'.
,
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-320/77-46 Docket No. 50-320 License No. CPPR-66 Priority Category a
-
Licensee:
Metropolitan Edison Company P.O. Box 542 Reading, Pennsylvania 19602 Facility Name:
Three Mile Island Nuclear Station, Unit 2 Inspection at:
Reading, Pennsylvania Inspection conducted: December 13, 1977 Inspectors:
MS/#m
/ >/2//77 6. lton, eac+pr Inspector date signed
/nxW a/a/77 n.
L. Narrow, Reactor Inspector date signed date signed Approved by:
h/
/ 2 /z/ /77
~
R. Haynes,Mef. Engineering Support cate signed Section No.1 RC&ES Branch Insoection Summary:
Inspection on December 13, 1977 (Recort No. 50-320/77-46)
Areas Inspected:
Routine, announced inspection of preservice examinations on steam generator tubes. The inspection involved 2.0 inspector-hours by two NRC inspectors.
Results: Of the one area inspected, no items of nonccmpliance were identified.
(
l Region I Form 12 j
(Rev. April 77)
74 g; iHO42505757
-
.
.
DETAILS 1.
Persons Contacted General Public Utilities Service Corcoration D. Mitchell, Engineer
,
Babcock and Wilcox Comoany D. Levstek, Engineer 2.
Licensee Action on Previous Insoection Findinas (0 pen) Unresolved Item (320/77-45-01):
Eddy Current indications found during examination of steam generator tubes.
The inspector visited the GPU Laboratories in Reading, Pennsylvania, to observe the condition of the steam generator tubes which had been removed from the A steam generator at Three Mile Island, Unit 2.
The tubes were removed to evaluate the results of an eddy current examination which was conducted after the hot functional test.
Further analyses were to be performed by the licensee to determine the nature and origin of the indications. The following conditions
-
were observed.
Tube 38-41 - Eddy Current test had detected wall reduction
--
greater than 40 percent. Visual observation under magnifi-cation disclosed three surface imperfections on the outside surface. The areas were less than 1/8 inch diameter and appear to be a type of defect associated with the manufacture of the tube.
Further analysis is being performed at the
laboratory.
--
Tube 133-78 - Eddy Current test had detected wall reduction of 1 to 3 mils deep. Visual observation under magnification disclosed slight surface removal on the outside surface of the tube.
It was evident that the surface removal was caueed by a grinding wheel and had probably occurred during fabrication of the steam generator.'
Tubes 71-28 and 47-70 - Eddy Current test had detected wall
--
reduction of less than 20 percent.
Visual observations dis-closed a change in the outside tube diameter at the location wall reduction. This appears to be associated with the adjustment ('
of the dies during the process of making the tubes.
No inside diameter change was apparent.
.
,
.
g
..s i
.
.
The licensee is continuing to analyze the tubes and Eddy Current inspection is in progress on the B generator.
This item is continued to be unresolved pending further inspection and examinations by the licensee to determine the cause and corrective actions required.
(320/77-46-01)
3.
Unresolved Items Areas for which more information is required to determine acceptability are considered unresolved. An unresolved item is contained in paragraph 2 of this report.
4.
Exit Interview At the conclusion of the inspection on December 13, 1977, the inspector met with the licensee representative named in paragraph 1 to discuss the inspection scope and findings.
.
d
%
.
.
.