ML081770311

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60-Day Response to the Reporting Requirements of NRC Order EA-03-009, Issuance of First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads.
ML081770311
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 06/25/2008
From: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BW080056, EA-03-009
Download: ML081770311 (4)


Text

June 25, 2008 BW080056 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License No. NPF-77 NRC Docket No. STN 50-457

Subject:

Braidwood Station Unit 2 60-Day Response to the Reporting Requirements of NRC Order EA-03-009, "Issuance of First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors"

Reference:

Letter from U. S. NRC, "Issuance of First Revised NRC Order (EA-03-009)

Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors," dated February 20, 2004.

The purpose of this letter is to provide the results of examinations performed at Braidwood Station Unit 2 in accordance with the requirements of the referenced NRC Order.

During the Spring 2008 (A2R13) refueling outage, Braidwood Station Unit 2 completed the visual inspection to identify potential boric acid leaks from pressure-retaining component above the reactor pressure vessel (RPV) in accordance with Section IV, paragraph D of the Order.

Section IV, paragraph E of the Order requires that the results of this examination be submitted to the NRC within 60 days after returning the plant to operation. The Braidwood Station Unit 2 Spring 2008 refueling outage ended on May 17,2008 and therefore the inspection results must be submitted by July 16, 2008.

June 25, 2008 U.S. Nuclear Regulatory Commission Page 2 Please direct any questions you may have regarding this submittal to Mr. David Gullott, Regulatory Assurance Manager, at (815) 417-2800.

Sincerely, Bryan Hanson Site Vice President Braidwood Station

Attachment:

A2R13 Reactor Vessel Head Visual Inspection Results

ecc: Illinois Emergency Management Agency - Division of Nuclear Safety Site Vice President - Braidwood Station Regulatory Assurance Manager - Braidwood Station Director, Licensing and Regulatory Affairs Manager, Licensing - Braidwood, Byron and LaSalle County Stations Braidwood Nuclear Licensing Administrator Braidwood Commitment Tracking Coordinator Exelon Document Control Desk Licensing

ATTACHMENT A2R13 Reactor Vessel Head Visual Inspection Results The examinations performed on the Braidwood Unit 2 reactor pressure vessel (RPV) head during the Spring 2008 refueling outage are contained in the first revised NRC Order EA-03-009 (Order),

Section IV, paragraph D and are summarized below.

Section IV, paragraph D states:

During each refueling outage, visual inspections shall be performed to identify potential boric acid leaks from pressure-retaining components above the RPV head.

For any plant with boron deposits on the surface of the RPV head or related insulation, discovered either during the inspections required by this Order or otherwise and regardless of the source of the deposit, before returning the plant to operation the Licensee shall perform inspections of the affected RPV head surface and penetrations appropriate to the conditions found to verify the integrity of the affected area and penetrations.

VISUAL EXAMINATION RESULTS During the Braidwood Station Unit 2, Spring 2008 refueling outage (A2R13) an initial walk down was performed with the unit in Mode 3 shortly after reactor shutdown to satisfy the requirements of Section IV, paragraph D. The walk down was performed in accordance with the requirements of the Order and the Braidwood Station Boric Acid Corrosion Control program. During this walk down, no evidence of boric acid leakage was observed. No boric acid was found on the mirror insulation below the nozzles. No new physical deposits were noted.

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