ML20057A402: Difference between revisions

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=Text=
=Text=
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20555


==Subject:==
==Subject:==
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==Dear Sir:==
==Dear Sir:==
 
Information regarding the indication that was found on the outside wall of the Unit 2 reactor pressure vessel was provided by a {{letter dated|date=August 18, 1993|text=letter dated August 18, 1993}}, as supplemented by an {{letter dated|date=August 25, 1993|text=August 25, 1993 letter}}.
Information regarding the indication that was found on the outside wall of the Unit 2 reactor pressure vessel was provided by a {{letter dated|date=August 18, 1993|text=letter dated August 18, 1993}}, as supplemented by an {{letter dated|date=August 25, 1993|text=August 25, 1993 letter}}.                     During an August 25, 1993 Conference call, the NRC staff requested that additional fracture mechanics analysis of the Unit 2 outside reactor vessel wall indication be performed. To this end, please find attached a report of the analysis that was performed.
During an August 25, 1993 Conference call, the NRC staff requested that additional fracture mechanics analysis of the Unit 2 outside reactor vessel wall indication be performed.
The report presents a discussion establishing a conservative upper bound on the accumulative uncertainty. The uncertainty includes the maximum possible error in sizing the flaw and accounts for possible variation in the cladding thickness. The fracture mechanics analysis also determines the allowable flaw size.
To this end, please find attached a report of the analysis that was performed.
The report presents a discussion establishing a conservative upper bound on the accumulative uncertainty.
The uncertainty includes the maximum possible error in sizing the flaw and accounts for possible variation in the cladding thickness.
The fracture mechanics analysis also determines the allowable flaw size.
The analysis concludes, that even considering the upper bound uncertainty, the flaw size continues to satisfy all ASME Section XI Code requirements; that is, the maximum allowable flaw size is greater than actual flaw plus uncertainty.
The analysis concludes, that even considering the upper bound uncertainty, the flaw size continues to satisfy all ASME Section XI Code requirements; that is, the maximum allowable flaw size is greater than actual flaw plus uncertainty.
Very truly yours, i
Very truly yours, i
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xc: Mr. S. D. Ebneter Regional Administrator, Region II
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;                          U. S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 l                         Atlanta, Georgia       30323 i
August 26, 1993 j.
Mr. George F. Maxwell l                         Senior NRC Resident Inspector, McGuire d-McGuire Nuclear Station f                         Mr. Victor Norses, Project Manager Office of Nuclear Reactor Regulation
page 2 1
!                          U. S. Nuclear Regulatory Commission l                         One White Flint North, Mail Stop 9H3
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{                         Washington, D.C.       20555
Mr.
!                          Mr. Nick Economos l                         U. S. Nuclear Regulatory Commission
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!                          101 Marietta Street, NW, Suite 2900 l                         Atlanta, Georgia       30323 1
D.
Ebneter Regional Administrator, Region II U.
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Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 l
Atlanta, Georgia 30323 i
Mr. George F.
Maxwell l
Senior NRC Resident Inspector, McGuire d-McGuire Nuclear Station f
Mr. Victor Norses, Project Manager Office of Nuclear Reactor Regulation U.
S.
Nuclear Regulatory Commission l
One White Flint North, Mail Stop 9H3
{
Washington, D.C.
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U.
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Latest revision as of 12:33, 17 December 2024

Forwards Rev 2 to Calculation MCC 1201.01-00-0027, Evaluation of Reactor Vessel OD Flaw, Per 10-yr ISI
ML20057A402
Person / Time
Site: Mcguire
Issue date: 08/26/1993
From: Mcmeekin T
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20057A403 List:
References
NUDOCS 9309140151
Download: ML20057A402 (2)
v • d • e


Text

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!!.. b n (71)lJ.Jy )[f r CL'b

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DUKE POWEH

,.c August 26, 1993 U.

S.

Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.

C.

20555

Subject:

McGuire Nuclear Station, Units I and 2 Docket Nos. 50-369 and 50-370 Unit 2 10 year Inservice Inspection Reactor Vessei outside wall indication

Dear Sir:

Information regarding the indication that was found on the outside wall of the Unit 2 reactor pressure vessel was provided by a letter dated August 18, 1993, as supplemented by an August 25, 1993 letter.

During an August 25, 1993 Conference call, the NRC staff requested that additional fracture mechanics analysis of the Unit 2 outside reactor vessel wall indication be performed.

To this end, please find attached a report of the analysis that was performed.

The report presents a discussion establishing a conservative upper bound on the accumulative uncertainty.

The uncertainty includes the maximum possible error in sizing the flaw and accounts for possible variation in the cladding thickness.

The fracture mechanics analysis also determines the allowable flaw size.

The analysis concludes, that even considering the upper bound uncertainty, the flaw size continues to satisfy all ASME Section XI Code requirements; that is, the maximum allowable flaw size is greater than actual flaw plus uncertainty.

Very truly yours, i

$ 1 i

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i i

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McMeekin ADOCK 05000367

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August 26, 1993 j.

page 2 1

xc:

Mr.

S.

D.

Ebneter Regional Administrator, Region II U.

S.

Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 l

Atlanta, Georgia 30323 i

Mr. George F.

Maxwell l

Senior NRC Resident Inspector, McGuire d-McGuire Nuclear Station f

Mr. Victor Norses, Project Manager Office of Nuclear Reactor Regulation U.

S.

Nuclear Regulatory Commission l

One White Flint North, Mail Stop 9H3

{

Washington, D.C.

20555 Mr. Nick Economos l

U.

S.

Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 l

Atlanta, Georgia 30323 1

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