GO2-06-082, Notification of Deviation from Boiling Water Reactor Vessel Internals Project (BWRVIP) Program Element

Notification of Deviation from Boiling Water Reactor Vessel Internals Project (BWRVIP) Program Element

ML061580062
Person / Time
Site:	Columbia
Issue date:	05/31/2006
From:	Coleman D Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-06-082
Download: ML061580062 (2)

Text

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-ENERGY NORTHWEST People- Vision. Solutions P.O. Box 968 e Richland, WA e 99352-0968 May 31, 2006 G02-06-082 U.S. Nuclear Regulatory Commission 10 CFR 50.55a ATTN: Document Control Desk Washington, D.C. 20555-000f

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 NOTIFICATION OF DEVIATION FROM BOILING WATER REACTOR VESSEL INTERNALS PROJECT (BWRVIP) PROGRAM ELEMENT

Reference:

Letter dated May 30,1997, Carl Terry (Chairman, BWRVIP) to Brian Sheron (NRC), "BWR Utility Commitments to the BWRVIP"

Dear Sir or Madam:

This letter is to notify the NRC of a deviation from a BWRVIP program element. This is a notification only and no action from the NRC is being requested. This notification is provided in accordance with the goals, objectives, and products of the agreements between the BWRVIP organization and the NRC described in the referenced letter.

The deviation is from a "needed" element of the BWRVIP program. The needed element is performing inspections in accordance with BWRVIP-03 "BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines," and the specif ic guidelines found in BWRVIP-1 8-A, "BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines."

During the spring 2005 refueling outage, reactor pressure vessel in-vessel visual inspections examined approximately 360 components from the BWRVIP program. A detailed critical review of the (recorded on DVD) examinations was performed after the outage to assess examination quality. Of the 360 components examined, 5 were found to have portions of the examination that deviate from the BWRVIP-03 and BWRVIP A guidelines. These components are identified in the table below along with the examination that was performed.

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NOTIFICATION OF DEVIATION FROM BOILING WATER REACTOR VESSEL INTERNALS PROJECT (BWRVIP) PROGRAM ELEMENT Page 2 BWRVIP Columbia BWRVIP Components Examination Examination Document Identification Description Criteria Performed BWRVIP- AS1-008 Lower Sparger EVT-1 (1/2 mil EVT-1 except 18 Core A T-Box Cover resolution) <10% VT-1 (1 mil Spray Plate Weld resolution)

BWRVIP- AS2-007 Lower Sparger EVT-1 (1/2 mil Should have 18 Core A Pipe to T- resolution) been closer.

Spray Box Weld <10% VT-i (1 mil resolution)

BWRVIP- DS4-271 Upper Sparger EVT-1 (1/2 mil EVT-1 except 18 Core DD EdCtC p to resolution) -z20%-tT-I1ftmi[

Spray Sparger . resolution)

BWRVIP- CS4-269 Upper Sparger EVT-1 (1/2 mil EVT-1 except 18 Core C End Cap to resolution) <10% VT-1 (1 mil Spray Sparger resolution)

BWRVIP- BS4-269 Lower Sparger EVT-1 (1/2 mil EVT-1 except 18 Core B End Cap to resolution) -15% VT-1 (1 mil 1_Spray Sparger resolution)

The subject welds have been examined during the first 14 refueling outages since plant startup to a 1 mil resolution with no degradation detected. They were examined in R-1 5 and R-16 to a 1/2 mil resolution with the same result. The welds will be inspected to BWRVIP-03 and BWRVIP-1 8-A guidelines (using the 11/2 mil resolution) during the next refuel outage (R-1 8) in spring 2007.

If you have any questions or require additional information regarding this matter, please contact Mr. GV Cullen, Licensing Supervisor, at (509) 377-6105.

Respectfully, DW Coleman Manager, Regulatory Programs Mail Drop PE20 cc: BS Mallet - NRC RIV BJ Benney - NRC NRR M Khanna - NRC BWRVIP Project Manager NRC Senior Resident Inspector/988C RN Sherman - BPA/1 399 WA Horin - Winston & Strawn