ML20035B683
| ML20035B683 | |
| Person / Time | |
|---|---|
| Issue date: | 03/25/1993 |
| From: | Tim Reed Office of Nuclear Reactor Regulation |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9304020313 | |
| Download: ML20035B683 (3) | |
Text
,
F March 25; 1993 Y
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.Mr. N. Liporslo, Manager
- Nuclear Safety and Regulatory 1
Activities l
Westinghouse Electric Corporation i
Nuclear and Advanced Technology: Division P. O. Box 355 Pittsburgh,= Pennsylvania 15230-0355 j
Dear Mr. Liparulo:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - NRC TASK GROUP ON INTERIM PLUGGING CRITERIA ISSUES l
The NRC staff met.with representatives of Westinghouse and industry on March 16 and 17, 1993, to discuss the ongoing effort of the interim plugging criteria task group.
In order to complete the task group's effort, we'need j
additional - information. Accordingly, please respond to the questions
-identified in the enclosure.
If you have any questions concerning this request, please contact me at (301) EW-1479.
j This request af.fects fewer than ten respondents and is, therefore, not subject to Office of Management & Budget review under P.L.96-511.
Sincerely,
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Timothy A. Reed, Project Manager i
Project Directorate II-3 j
Division of Reactor Projects-l/II Office of Nuclear Reactor Regulation
Enclosure:
DISTRIBUTION Request for Additional Central File 50 JStrosnider 704 l
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cc w/ enclosure:
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Division P. O. Box 355 Pittsburgh, Pennsylania 15230-0355 i
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March 25, 1993 Mr. N. Liparulo, Manager Nuclear Safety and Regulatory Activities Westinghouse Electric Corporation Nuclear and Advanced Technology Division P. O. Box 355 Pittsburgh, Pennsylvania 15230-0355
Dear Mr. Liparulo:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - NRC TASK GROUP ON INTERIM PLUGGING CRITERIA ISSUES The NRC staff met with representatives of Westinghouse and industry on March 16 and 17, 1993, to discuss the ongoing effort of thc interim plugging criteria task group.
In order to complete the task group's effort, we need additional information. Accordingly, please respond to the questions identified in the enclosure.
If you have any questions concerning this request, please contact me at (301) 504-1479.
This request affects fewer than ten respondents and is, therefore, not subject to Office of Management & Budget review under P.L 96-511.
Si e ely, imothy A.
eed, Project Manager Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ enclosure:
Mr. Bob Sterdis Westinghouse Electric Corporation Nuclear and Advanced Technology Division P. O. Box 355 Pittsburgh, Pennsylania 15230-0355 Mr. Tom Pitterle Westinghouse Electric Corporation Nuclear and Advanced Technology Division P. O. Box 355 Pittsburgh, Pennsylvania 15230-0355
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/
ENCLOSURE
\\
I Request for Additional Information Interim Plugging Group Task Group 1.
Provide material presented during the March 16-17, 1993, meeting.
Indicate in the submittal what information is proprietary.
2.
Provide a written discussion of why the beginning-of-cycle and end-of-cycle crack length and depth distributions used in the NRC analysis are inconsistent with inspection results.
Include, for example, the number of through-wall defects projected by the NRC analysis method with actual plant inspection results.
3.
Provide details of the analyses + hat were performed to benchmark the NRC analysis method using the results of experimental leakage tests.
Include comparisons made for the 7/8" and 3/4" diameter pulled tube and model boiler data.
Include in the submittal sufficient data (e.g.,
crack dimensions, leakage rates as a function of pressure) for NRC to independently perform the comparisons.
4.
Provide details of the Begley-Houtman model used for predicting ligament failure for partial through-wall cracks.
5.
Provide results of review of ECT data or tube examinations, if possible, to determine if defects outside of the tube support plates were in regions of sludge build deposits.
Include a discussion of the ability to measure the depth of sludge deposits on top of tube support plates, and discuss current estimates of the extent and height of sludge piles r
typical in operating plants.
6.
a)
Provide an analysis of the probability of detection (P0D) for outside diameter stress corrosion cracks (ODSCC) for bobbin coil and rotating pancake coil eddy current testing.
b)
Provide the data used in performing these analyses in a form r9ch that the NRC can perform independent statistical evaluations.
Also, include the sources of the data, and a discussion of how prototypic the defects and the inspection methods were when the examinations of the tubes were performed.
For data that are based on plant examinations and tube pulls, indicate the plants from which the data came and how prototypic the degradation in the i
steam generators was when the tubes were removed from service.
c)
Discuss the probability of detection of ODSCC for intersections in i
sections of tubes that must be inspected with reduced diameter probes due to prior sleeving operations. Discuss how this situation is being dealt with in plant inspections.
l 7.
Discuss how the POD (or probability of non-detection) is, or could be, incorporated in the model for assessing the potential for tube rupture and tube leakage u1 der voltage based plugging criteria.
l