ML20212G431

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Requests That Encl Draft Document Be Provided to NRC & Local Pdrs,Per NRR Ofc Ltr 43.Draft Provided to Util
ML20212G431
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 03/04/1987
From: Heitner K
NRC
To:
NRC
References
NUDOCS 8703050347
Download: ML20212G431 (3)


Text

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if y 3 -NUCLEhR' REGULATORY COMMISSION WASHINGTON, D. C. 20555 5 j i l '% . . . . . $ .

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O. With regard to the Fort St. Vrain '(FSV) Technical Specifications, 5.3.11

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Stea'm Generator Bimetallic Welds Surveillance and'SR 5.3.12 - Steam Generator Tube Leaks Surveillance, describe the results of the surveillance requirements including the number of times and the dates that they have been implemented. " Provide"eny other information that is

- available concerning degradation of >the steam generator tubes.

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/f'd The following questions refer to the document entitled "Effect of

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y4 Firewater Cooldown Using EES Bundle on Steam Generator Structural Integrity" '

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1. It is stated that Sanicro 31 reheater tube material is'a, European Alloy c

f ^'G;-type,,materialwhichmettherequiredmaterial'spehificationsof 80

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Alloy 800 Grade 2 at the time when the stedci generators we,he built.

Provide the che"iical composition of this material and its strength levels

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(i.e, yield inJ ultimate strengths at appropriate temperatures) In addition address the metallurgical treatment of Sanicro 31 in comparison with the treatment of the ASME Code, Alloy 800 mat'erial. Further, explain why the Sanicro 31 will not degrade to below the minimum levels allowed for the Code material because of the temperature cycles which the steam generator tubes experience. ,

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2. .?t?isgimplied that Sa'nicro 31 is equivalent to an Alloy 800 H material, v

e.g., SG-163 or SG-407. If this is the case justify the value of 23,300 '

psi at 380 F for S,. -Current ASME Code values indicate S, values of 16,700 psi for SB-163 and 20,000 psi for SB-407 at 380 F.

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3. , Figure 4.4 is incomplete as submitteid. The temperature profile for the

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i: t  ! ' time in hours from D to 2 is missing. Please supply this information.

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The possibility of accumulated creep-fatigue damage contributing to tube p 'l) ,(',' i~1:

4 io failure is; not explicitly addressed in this submittal. Please provide an evaluation of this potential failure mechanism in the context of the Us creepicollapse failure mode' that was assumed.

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