ML20198E165

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Forwards Relief Request from Performing Reactor Nozzle Surface Exam Per 1977 ASME Section XI Code.Request Based on ALARA Concerns & Ability to Achieve High Quality Data by Remotely Conducting Full Volumetric Exam of Weld
ML20198E165
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 11/30/1992
From: Skolds J
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9212040247
Download: ML20198E165 (2)


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-- South CIrolina Electric & ois Ctmp:ny John L skolde l

'i P.O. Dor 88

' Ves President

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Jenkinsville. SC 29065 Nucisar Operations -

4 (803) 345 4040 SCE&G:

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NOVEM3ER 30, '1992 1

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Document Control Desk U. S. Nuclear Regulatory Commission-

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Washington, DC_ 20555 Gentlemen:

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Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)

DOCKET NO. 50/395 OPERATING LICENSE N0..NPF-12 REACTOR N0ZZLE SURFACE EXAMINATION RELIEF REQUEST-l (NRR920005).

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. South Carolina Electric &' Gas Company (SCE&G), hereby submits.the attached request for relief.from performing Reactor Nozzle Surface' Examination as required by.the'1977 ASME Section XI Code. :This' request is based.on-ALARA.

j concerns and the ability to acquire higher quality data by remotely conducting a full' volumetric examination of the weld. SCE&G is submitting-the attached relief request in accordance with 10CFR50.55a(a)(3)(ii).-

In order to support the scheduling of activities ~for.the'upcomingJoutage at

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the VCSNS, SCE&G requests the NRC response,and approval of this request by l-January 31, 1993.

i Should you have any questions, please call David Ha11e atf(803) 345-4322.

Very truly yours, John L. Skolds DCH:JLS:smd-Attachment c:.

O. W. Dixon.

.NRC Resident-. Inspector

-R.-R. Mahan J.-B.LKnotts Jr.

R.-J. White NSRC-S. 0.1Ebneter' RTS: (NRR.920005 File (810.19-2) )

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NUCLEAR-' EXCELLENCE --A SUDMER' TRADITION!

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Attachment. to. Document Control Desk Le'tter -

j NRR 920005 Pa,ga 1 of.1 Reactor Nozzle Surface Examination Relief-Request Components: Reactor Vessel.0utlet Nozzle Safe End' Welds-Code Class 1 (See List Below)

Table IWB-2500-l'

[

isometric Drawina No.

Weld No.

Cateaory item No.

l-CGE-1-4100 1*

B-F B5.10 CGE-1-4200 1*

B-F B5.10 CGE-1-4300 1*

B-F B5.10-CGE-1-4100 16*

B-F B5.10 CGE-1-4200 16*

B-F B5.10 i

CGE-1-4300 16*

B-F B5.10 l

CGE-1-4100 2

B-J B9.11 CGE-1-4200 2

B-J 89.11 1

CGE-1-4300 2

B-J 89.11 i

CGE-1-4100 15 B-J 89.11 CGE-1-4200 15' B-J 89.11 l

CGE-1-4300 15 B-J B9.11

  • Dissimilar Metal Code Requirement:

ASME Boiler and Pressure Vessel Code,Section XI, 1977 Edition including-Summer 1978 Addenda, Table 1WB-2500-1, Category B-F: Item B5.10 and.

Category B-J: Item 89.11, requires the following:

All welds identified above are to have surface examinations and inner one-4 third volumetric ~ examinations performed in accordance with figure IWB-t 2500-8..

Alternate Test:

Perform a full volumetric examination of the weld to the extent practical as noted by Code Case N-460, and discontinue the surface examination.

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Basis for Relief:

A full volumetric examination is a more thorough examination than. the surface and one-third volumetric examination currently required.

The alternate-test will-provide an increased ability 1to identify indications that may exist in the entire region of the-weld. 'Also, because the-examination can be performed in conjunction with the reactor vessel examination, the alternate test reduces the estimated: dose received for the inspection by 2.0 REM. Therefore, the alternate test reduces a radiation exposure hardship and provides an acceptable method of 4

inspecting the welds without affecting the quality and safety of-the plant.

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