ML19206B250

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Safety Evaluation of once-through Steam Generator Instrumentation Program
ML19206B250
Person / Time
Site: Crane Constellation icon.png
Issue date: 11/01/1977
From:
METROPOLITAN EDISON CO.
To:
Shared Package
ML19206B249 List:
References
ZAR-771101, NUDOCS 7905080175
Download: ML19206B250 (4)
v • d • e


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Steven A. Va ga, Chief November 22, 1977 CQL 1632 4.

"0TSG Enclosure Can Analysis".

Menbers of my staf f will be happy to discuss any questicas concerning this installation at any tine.

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Safety Evaluation of OTSG Instrunentation Program Lt_

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. structural codifications have been constructed

  • in accordance with an appropriate equipment' specification (Reference 2).

The require =ents of this specification assure that the structural integrity of individual components as well as the total OTSG in its final configuration will be as good as, or better than, that previously described in the FSAR.

The detailed stress calculations and associated verifications presented in Reference 3 were perforced to shcw cocpliance to the equipment specifica-tion.

Considerotion of the preceding information demonstrates that the struc-tural integrity of the OTSG has not been degraded, and the probability of an accident previously evaluated is not increased.

In addition, the probability of an accident occurring which has not been previously evaluated or described in the FSAR, is not increased.

The consequences of an accident.cm be regarded to be increased by (1) f ailure of additional structure due to loads induced by the initial accident condition and/or (2) failure of safety related equipment to perform as expected.

With regard to item (1), above, the equipment specification includes consideration of accident induced loads for structures constituting a primary or secondary side pressure retaining boundary.

Inf o rma tion presented above provides sufficient assurance that additional structures will not fail and that the consequences of such an accident will not be increased by this mechanism. With regard to item (2), there will be no piece of hardware directly related to safety which will be modified.

Neither the structural integrity nor the operational characteristics of any

" safety related equipment" is affected.

Field measure =ent programs at Oconee Nuclear Station Units #1 and #2 were similar in scope and arrangement to the present TMI-2 program. At Oconee 41, ther=occuples were installed within OTSG tubes, lead wires run through internal routing hardware on the OTSC upper tubesheet and upper head, and lead wires exited through fittings in the inspection opening cover. This hardware was in the OTSG for one full fuel cycle (April 1973 through October 1974). At Oconee 12, acceleroceters were installed within OTSG tubes, lead wires run through internal routing hardware on the OTSG upper tubesheet and upper head, and lead wires exited through fittings in the inspection opening covers. This hardware has been in the OTSG since July 1977

  • The term " construe:1on" as used herein is an all-inclusive ters com-prising the caterials, design, f ab rication, examination, testing, installation, and inspection of the subject hardware.

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