ML061950009

Facsimile Transmission, Draft Request for Additional Information Regarding Relaxation Request IR-2-46, Reactor Pressure Vessel Head Inspections

ML061950009
Person / Time
Site:	Millstone
Issue date:	07/14/2006
From:	Nerses V Plant Licensing Branch III-2
To:	Poole B Plant Licensing Branch III-2
Nerses V, NRR//DLPM, 415-1484
References
EA-03-009, TAC MD1735
Download: ML061950009 (3)

Text

July 14, 2006 MEMORANDUM TO: Brooke D. Poole, Acting Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Victor Nerses, Senior Project Manager /RA/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

MILLSTONE POWER STATION, UNIT NO. 3 - FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING RELAXATION REQUEST IR-2-46, REACTOR PRESSURE VESSEL HEAD INSPECTIONS (TAC NO. MD1735)

The attached draft request for additional information (RAI) was transmitted on July 14, 2006 to Mr. Paul Willoughby, at Dominion Nuclear Connecticut, Inc. (DNC) by facsimile. This was done to support a telephone conversation to facilitate the review being conducted by the Nuclear Regulatory Commission (NRC) staff in order to clarify certain items in the licensees submittal. The draft RAI is related to DNCs submittal dated May 16, 2006, regarding a request for relaxation to the reactor pressure vessel head inspection requirements of the First Revised NRC Order (EA-03-009). Review of the draft RAI will allow DNC to determine and agree upon a schedule for response to the RAI. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-423

Enclosure:

As stated

July 14, 2006 MEMORANDUM TO: Brooke D. Poole, Acting Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Victor Nerses, Senior Project Manager /RA/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

MILLSTONE POWER STATION, UNIT NO. 3 - FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING RELAXATION REQUEST IR-2-46, REACTOR PRESSURE VESSEL HEAD INSPECTIONS (TAC NO. MD1735)

The attached draft request for additional information (RAI) was transmitted on July 14, 2006 to Mr. Paul Willoughby, at Dominion Nuclear Connecticut, Inc. (DNC) by facsimile. This was done to support a telephone conversation to facilitate the review being conducted by the Nuclear Regulatory Commission (NRC) staff in order to clarify certain items in the licensees submittal. The draft RAI is related to DNCs submittal dated May 16, 2006, regarding a request for relaxation to the reactor pressure vessel head inspection requirements of the First Revised NRC Order (EA-03-009). Review of the draft RAI will allow DNC to determine and agree upon a schedule for response to the RAI. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-423

Enclosure:

As stated DISTRIBUTION:

PUBLIC LPL1-2 R/F RidsNrrPMGMiller RidsNrrLACRaynor RidsNrrDorlLpl1-2 ADAMS Accession Number: ML061950009 OFFICE LPL1-2/PM LPL1-2/LA CNPB/BC NAME VNerses:rsa CRaynor TChan (AKeim for)

DATE 7/14/06 7/14/06 7/14/06 OFFICIAL RECORD COPY

DRAFT REQUEST FOR ADDITIONAL INFORMATION MILLSTONE POWER STATION, UNIT 3 RELAXATION REQUEST IR-2-46 ALTERNATIVE REACTOR VESSEL HEAD INSPECTION CRITERIA DOCKET NO. 50-423 By letter dated May 16, 2006, Dominion Nuclear Connecticut, Inc. (DNC, the licensee) submitted a request for relaxation to the reactor pressure vessel (RPV) head inspection requirements of the First Revised NRC Order (EA-03-009). The Nuclear Regulatory Commission (NRC) staff requests the following additional information to complete its review.

1. Provide details of the attachment of the guide funnel to the nozzle, including details of the weld length, size, filler material type, etc.

2. Describe how the weld attaching the guide funnel to the nozzle will affect the ability of the ultrasonic test, from the inner diameter of the nozzle, to detect flaws.

3. When determining the operating stresses in the nozzle at the top of the guide funnel, how will the weld attaching the guide funnel to the nozzle be taken into consideration?

4. In the second paragraph under the reason for request, a distance is referred to. The paragraph states: Based on comparison with similarly designed RPV closure heads, this distance is reasonably estimated at less than 1.0-inch. What distance is this referring to?

5. Approval of the licensees relief request is dependent on the NRC staff evaluating the results of the licensees complete structural integrity evaluation and making a finding that it is acceptable. DNC stated that it will provide this information to the NRC before entry into Mode 4 following refueling. What is the earliest estimated date that this information for the structural evaluation can be provided? That is, can the evaluation be completed sooner for a variety of distances from toe of the J-grove weld to the top of the funnel?

Enclosure