ML20024B569

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Preliminary Rept of Safety Concerns Re Small Break LOCA Not Conforming to 10CFR50.46 Requirement
ML20024B569
Person / Time
Site: Crane  Constellation icon.png
Issue date: 04/04/1978
From: Dunn B, Nirodh Shah
BABCOCK & WILCOX CO.
To:
References
TASK-*, TASK-GB GPU-0616, GPU-616, NUDOCS 8307090236
Download: ML20024B569 (3)


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I PREt.IMI'hiRY REPORT OF 3AFETY CONCERNS d

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205 TA T4.4 h.y

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On )tarch 30, 1978, while checking the adequacy este a see

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of a 6 foot Auxiliary Teodwataar (AFW) level con trol for a generie 205 TA plante, it was found

$.4b that the results of a certain: :email break LOCA 4 se un senuna is us naut Oves S ee do not conform to the requirements of 10 CTE.

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All generic 205 TA plants. CEIO (Erie) T7A (Bellefonte). VFPSS (1,2), PGE (Febble 3.*

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el esscesetsee se saettv susses.setetsew aseractge ca eests:(s). susnets) es actsestesseerute. ase smeset es p.,

sarste et etset useatsees Tor a 0.C5 ft2 break at pump Eischarge, the core uncovers by a two phase misture to Q

the extent that the core cond2:1on may not conform to the requirements of the

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10 CTR 53.46.

y A 40 foot AFW 1evel control ibt :the past have resulted in an acceptable result.

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3 The design change to a 6 foot control does not provide a safe, acceptable result..

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For a safe plant ~ operation, t!he system design needs to be'sodified to avoiit the un.

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acceptable consequences of a. 6 foot AFV level control.

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~ Corrective actions, identified! aut not initiated, are described in the Attachment A.

The actions emphasize either a calculational improvement and/or a hardware change.

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Described corrective action completed /to be initiated (Continued)

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_3 Corrective itesa are identified, but not limited to the following lists

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Analysis (model) research Wi:

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Zaloudek-Moody leak discharge model instead of the Bernau111-Noody p*'

model.

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10% uncertainty on ANS Decay Heat generation data af ter 1000 seconds Y:

instead of the 20% margin. This fix could require a rule change.

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Increase in the steam generator level set. Make the 40 foot Arv y.:.

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level control safety grade.

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Operator Action. Depressurias the primary or the secondary side by Q

the operator action.

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Increase the RF1 capacity or availability..

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Investigate the feasibility of a break size of the' order of 0.05 f t 7:

in the pump discharge piping.

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Derate the plant power level.

' A-9.~~Use rated conditions and/or as-built data.to do a plant by plant I.f-fM

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analysis instead of a generic analysis.

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