ML19210D236
| ML19210D236 | |
| Person / Time | |
|---|---|
| Issue date: | 10/22/1979 |
| From: | Riggs R Office of Nuclear Reactor Regulation |
| To: | Check P Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19210D237 | List: |
| References | |
| NUDOCS 7911260184 | |
| Download: ML19210D236 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMM.JSION 3 J-
.E WASHINGTON, D. C. 20555 s
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%.'....S OCT 2 21979 MEMORANDUM FOR: Paul S. Check, Chief, Reactor Safety Branch, Division of 0,,erating Reactcrs THRU:
Franklin D. Coffman, Section Leader, Section B, Reactor Safety Branch, Division of Operating Reactors FROM:
Robert Riggs, Reactor Safety Branch, Division of Operating Reactors
SUBJECT:
MEETING
SUMMARY
On October 12, 1979, members of the NRC staff met with members of the Westinghouse staff. The list of Attendees is provided in Attachment A.
s The purpose of the meeting was to discuss Westinghouse data and analysis techniques related to control rod guide thimole wear.
The Agenda of the meeting followed the format as provided in Attachment B.
During the meeting, Westinghouse discussed and provided " Draft" responses to questions the NRC staff formulated (References 1 and 2) concerning previous Westinghouse subnittals (References 3, 4 and 5) on this subject.
The information was supplemented during the discussion by additional " Draft" material. The contents of the " Draft" naterials and the discussions are proprietary to Westinghouse.
At the end of the presentation, the NRC staff concluded that the information provided by Westinghouse was responsive to the NRC questions of References 1 and 2 with one exception: The one exception was related to confirmatory surveillance (question 4 of References 1 and 2) which will be redrefted for NRC comment prior to issuance of the formal response.
The consenses of opinions by the NRC staff was as follows:
- 1) No throughwall wear was observed in control rod guide thimbles in Westinghouse fuel at Westinghouse NSSS facilities.
- 2) P.stinghouse techniques for measuring the guide thimble wear appear accepta bl e.
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Paul S. Check OCT 2 21979
- 3) The analysis techniques used by Westinghouse to assess the structural integrity of worn thimbles are adequately conservative provided the conservatism of the Nestingl.ause mechanistic wear model can be confirmed. -
4). The bounding analysis submitted by Westinghouse for the 15x15 and 17x17 fuel design should be ccafirmed by PIE examination (see exception above).
The formal Westinghouse response to our cuestions or guide thimble wear will be submitted by early November 1979, assuming that a satisfactory resolution of the one exception (additional surveillance of 16x15 and 17x17 fuel) can be worked out. At that time, 00R will issue a letter addressing NRC acceptance of the Westinghouse analysis o.f the guide thimble wear problem. DSS will address acceptability on the docket of each new plant in question.
The D0R and DSS statements should be fully coordinated through R. Riggs (RSB/ DOR) and D. Powers (CPB/ DSS).
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Robert Riggs Reactor Safety Branch Division of Operating Reactors
Enclosure:
As stated References 1.
B. K.' Grimes (USNRC) letter to T. M. Anderson (W), dated September 7,1979.
2.
K. Kniel (USNRC) memorandum to 0. Parr (USNRC), " Guide Thimble Tube Wear in Westinghouse Fuel Assemblies," September 4,1979.
3.
T. M. Anderson (W), letter (NS-TMA-1936) to D. G. Eisenhut (USNRC), dated September 12, 1978.
4.
T. M. Anderson (W) letter (NS-TMA-1992) to D. G. Eisenhut (USNRC) dated December 15, 1578.
5.
T. M. Anderson (W) letter (NS-TMA-2102) to D. G. Eisenhut (USNRC), dated June 27,1979.
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ATTACHMENT A Attendees - 10/12/79 R. Riggs RSB/ DOR J. Reavis W NFD G. Antaki U'NFD M. Arlotti s' NFD F. Ellingson U' NFD R. O. Meyer CPB/ DSS D. A. Powers CPB/ DSS F. D. Coffman RSB/ DOR D. K. Hsu Public Service Electric & Gas N. P. Wol fhope VEPC0 D. J. Vito STSG/ DOR /NR P. C. Wagner STSG/ DOR /NRC D. Houston CPB/ DSS R. Label RSB/ DOR T. Heitman Duke Power M. Connor ORB / DOR S. Sands RSB/ DOR T. Alexion RSB/ DOR L. G. Pilgrim W NFD iT i
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