ML19326D549: Difference between revisions

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77  Gratun of the Report on Reactor Vesse! Surveillant c Specimen Holder Tnbes V
77  Gratun of the Report on Reactor Vesse! Surveillant c Specimen Holder Tnbes V
This report han been written to provid'c infornation on the statun of the reportabic deficiency on the reactor vessel surveillance specimen bc,1 der tubes (SSilT) reported in conformance with 10 CFR 50.55e.
This report han been written to provid'c infornation on the statun of the reportabic deficiency on the reactor vessel surveillance specimen bc,1 der tubes (SSilT) reported in conformance with 10 CFR 50.55e.
Current Status The SSl!T for B&W 177 fuel assembly plants has been redesigned and prototype testing has been comp?.cted which verifies the adequacy of this new design. The redesign is described in B&W Topical Report BAU-10051, Supplement 1 " Design of Reactor Internals and Incore Instrument Nozzles for Floe Induced Vibration -
Current Status The SSl!T for B&W 177 fuel assembly plants has been redesigned and prototype testing has been comp?.cted which verifies the adequacy of this new design. The redesign is described in B&W Topical Report BAU-10051, Supplement 1 " Design of Reactor Internals and Incore Instrument Nozzles for Floe Induced Vibration -
Structural Analysis of 177-F.A'. Redesigncd Surveillance Specimen Holder Tubes" and the prototype test program conddeted at Davis Ecsce Unit 1 is described in D&W Topical Report BAW-10038, Supplement 1,' " Prototype Vibration Measurement Program for Reactor Internals". Both of these reports were submitted to NRC in Augu st, 1976,                              -
Structural Analysis of 177-F.A'. Redesigncd Surveillance Specimen Holder Tubes" and the prototype test program conddeted at Davis Ecsce Unit 1 is described in D&W Topical Report BAW-10038, Supplement 1,' " Prototype Vibration Measurement Program for Reactor Internals". Both of these reports were submitted to NRC in Augu st, 1976,                              -
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The successful results of the prototype qualification and the minor design improvements made as a result of this testing were summarized to acabers of the NRC Staff in a meeting held February 9,1976 with B&W and Toledo Edison.
The successful results of the prototype qualification and the minor design improvements made as a result of this testing were summarized to acabers of the NRC Staff in a meeting held February 9,1976 with B&W and Toledo Edison.
These results. are to be further documented in a B&W Topical Report to be submitted to NRC in April, 1977.      NRC Staff approval of the redesigned SSHT and the qualification as a prototype is anticipated fallowing review of this report.
These results. are to be further documented in a B&W Topical Report to be submitted to NRC in April, 1977.      NRC Staff approval of the redesigned SSHT and the qualification as a prototype is anticipated fallowing review of this report.
The review schedule for this report has not yet been developed, however, the report will be referenced by other B&W plants scheduled to startup in 1977.
The review schedule for this report has not yet been developed, however, the report will be referenced by other B&W plants scheduled to startup in 1977.
The original SSHT design has been removed from the Midland 1&2 internals and procurc=ent of the redesigned SSilT's for installation at Midland is prc-cceding. The Midland FSAR will describe this new design and incorporate the above B&W Topical Reports by reference.
The original SSHT design has been removed from the Midland 1&2 internals and procurc=ent of the redesigned SSilT's for installation at Midland is prc-cceding. The Midland FSAR will describe this new design and incorporate the above B&W Topical Reports by reference.
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* 8006180        [76                    .
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Latest revision as of 00:03, 1 February 2020

Interim Deficiency Rept Re Reactor Vessel Surveillance Holder Tubes.Tube Redesign Verified by Prototype Testing & New Tube Procurement Is Proceeding
ML19326D549
Person / Time
Site: Midland
Issue date: 03/30/1977
From:
BABCOCK & WILCOX CO.
To:
Shared Package
ML19326D541 List:
References
NUDOCS 8006180695
Download: ML19326D549 (1)
v • d • e


Text

_ _ _ . __ . _ _ _ _. _ _ _ . . .

m '

77 Gratun of the Report on Reactor Vesse! Surveillant c Specimen Holder Tnbes V

This report han been written to provid'c infornation on the statun of the reportabic deficiency on the reactor vessel surveillance specimen bc,1 der tubes (SSilT) reported in conformance with 10 CFR 50.55e.

Current Status The SSl!T for B&W 177 fuel assembly plants has been redesigned and prototype testing has been comp?.cted which verifies the adequacy of this new design. The redesign is described in B&W Topical Report BAU-10051, Supplement 1 " Design of Reactor Internals and Incore Instrument Nozzles for Floe Induced Vibration -

Structural Analysis of 177-F.A'. Redesigncd Surveillance Specimen Holder Tubes" and the prototype test program conddeted at Davis Ecsce Unit 1 is described in D&W Topical Report BAW-10038, Supplement 1,' " Prototype Vibration Measurement Program for Reactor Internals". Both of these reports were submitted to NRC in Augu st, 1976, -

The successful results of the prototype qualification and the minor design improvements made as a result of this testing were summarized to acabers of the NRC Staff in a meeting held February 9,1976 with B&W and Toledo Edison.

These results. are to be further documented in a B&W Topical Report to be submitted to NRC in April, 1977. NRC Staff approval of the redesigned SSHT and the qualification as a prototype is anticipated fallowing review of this report.

The review schedule for this report has not yet been developed, however, the report will be referenced by other B&W plants scheduled to startup in 1977.

The original SSHT design has been removed from the Midland 1&2 internals and procurc=ent of the redesigned SSilT's for installation at Midland is prc-cceding. The Midland FSAR will describe this new design and incorporate the above B&W Topical Reports by reference.

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  • 8006180 [76 .

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