ML040770235

Draft Information Inputs Steam Generator Inspection Report - Attachment 8

ML040770235
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/29/2004
From:	Alexion T Office of Nuclear Reactor Regulation
To:	Sharon Bennett Office of Nuclear Reactor Regulation
Alexion T W, NRR/DLPM, 415-1326
Shared Package
ML040820923	List: ML040770226 ML040770235 ML040770247 ML040770253 ML040770256 ML040770261 ML040770265 ML040770270 ML040770274 ML040820903
References
Download: ML040770235 (3)

Text

Thormas Alexion - EXPANSION OF QUESTION 5 - ANO-1 STEAM GENERATOR INSPECTION REPORT . . .

, Page 11 From: Thomas Alexion To: BENNETT, STEVE A Date: 1/29/04 10:36AM

Subject:

EXPANSION OF QUESTION 5 - ANO-1 STEAM GENERATOR INSPECTION REPORT Steve, See the attached.

Tom

C:\WINDOWS\TEMP\GW)00001 .TMP Page 1.1 AMail Envelope Properties (4019286D.BC6: 0: 20628)

Subject:

EXPANSION OF QUESTION 5 - ANO-1 STEAM GENERATOR INSPECTION REPORT Creation Date: 1/29/04 10:36AM From: Thomas Alexion Created By: TXVA @nrc.oov Recipients Action Date & Time entergy.com Transferred 01/29/04 10:36AM SBENNE2 (BENNETT, STEVE A)

Post Office Delivered Route entergy.com Files Size Date & Time Murphy.wpd 5604 01/28/04 03:OOPM MESSAGE 657 01/29/04 10:36AM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard Reply Requested: No Return Notification: None Concealed

Subject:

No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened

Expansion of Question #5 from the Previous RAI Steam Generator Inspection Report Arkansas Nuclear One. Unit 1

1. What is the acceptance criterion that is being used?

2. What is the basis / derivation of the acceptance criterion?

3. If the acceptance criterion is expressed in terms of post-accident dose or if the acceptance criteria was backcalculated from dose, please explain the significant assumptions and inputs that are used to calculate the dose from the measured leakage and vice versa.

4. Are the methodology, assumptions and inputs of these analyses consistent with regulatory guidance for design basis accidents?

5. Provide summary description of how the 1.87 gpm leak rate estimate was determined for LBLOCA. This should include the following information:

a. Does this estimate consider leakage from flaws other than circumferential cracks?

b. Brief description of method used to calculate leakage for circumferential cracks in the original roll or heat affected zone adjacent to the tube-to-tubesheet seal weld if no reroll is present.

c. Brief description of method used to calculate leakage for circumferential cracks at or below lower transition of original roll if no reroll is present.

d. Brief description of method used to calculate leakage for circumferential cracks at reroll repair.

e. Brief description of method used to calculate leakage for circumferential cracks inboard of reroll repair.

f. Brief description of method used to calculate leakage for circumferential cracks outboard of reroll repair. Are the portions of tubing outboard of reroll repairs subject to inspection?