L-04-128, Supplemental Response to NRC Bulletin 2004-01

Supplemental Response to NRC Bulletin 2004-01

ML042780378
Person / Time
Site:	Beaver Valley
Issue date:	09/29/2004
From:	Pearce L FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BL-04-001, L-04-128
Download: ML042780378 (2)

Text

FENOC Beaver Valley Power Station Route 168 PO. Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077-0004 L William Pearce 724-682-5234 Size Vice President Far: 724-643-8069 September 29, 2004 L-04-128 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station (BVPS), Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Supplemental Response to NRC Bulletin 2004-01

References:

l. NRC Bulletin 2004-01, "Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors," dated May 28, 2004.

2. FirstEnergy Nuclear Operating Company (FENOC) 60-Day Response to NRC Bulletin 2004-01 for BVPS (Letter L-04-081 dated July 27, 2004).

NRC Bulletin 2004-01 (Reference 1) was issued to advise licensees that current methods of inspecting Alloy 82/182/600 materials used in the fabrication of pressurizer penetrations and steam space piping connections may need to be supplemented with additional measures to detect and adequately characterize flaws due to primary water stress corrosion cracking (PWSCC).

All pressurized-water reactor licensees were requested to submit a response within 60 days of the date of the Bulletin. FENOC provided a response to the Bulletin for BVPS Unit I and 2 on July 27, 2004 (Reference 2).

Based on a telecon with the NRC staff on September 22, 2004, supplemental information was requested with regard to the response to Item (1)(c) of the Bulletin. In response to the request, if circumferential cracking is observed in either the pressure boundary or non-pressure boundary portions of any locations covered under the scope of the Bulletin, FENOC will enter the issue into the BVPS Corrective Action Program, develop plans to perform an adequate extent-of-condition evaluation, and will discuss those plans with cognizant NRC technical staff prior to restarting the affected unit.

97/C)

I Beaver Valley Power Station, Unit No. I and No. 2 Supplemental Response to NRC Bulletin 2004-01 L-04-128 Page 2 No new commitments are contained in this submittal. If there are any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Compliance at 724-682-5284.

I declare under penalty of perjury that the foregoing is true and correct. Executed on September 21 , 2004.

Sincerely, L. William Pearce Attachments c: Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Sr. Resident Inspector Mr. S. J. Collins, NRC Region I Administrator

Text

FENOC Beaver Valley Power Station Route 168 PO. Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077-0004 L William Pearce 724-682-5234 Size Vice President Far: 724-643-8069 September 29, 2004 L-04-128 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station (BVPS), Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Supplemental Response to NRC Bulletin 2004-01

References:

l. NRC Bulletin 2004-01, "Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors," dated May 28, 2004.

2. FirstEnergy Nuclear Operating Company (FENOC) 60-Day Response to NRC Bulletin 2004-01 for BVPS (Letter L-04-081 dated July 27, 2004).

NRC Bulletin 2004-01 (Reference 1) was issued to advise licensees that current methods of inspecting Alloy 82/182/600 materials used in the fabrication of pressurizer penetrations and steam space piping connections may need to be supplemented with additional measures to detect and adequately characterize flaws due to primary water stress corrosion cracking (PWSCC).

All pressurized-water reactor licensees were requested to submit a response within 60 days of the date of the Bulletin. FENOC provided a response to the Bulletin for BVPS Unit I and 2 on July 27, 2004 (Reference 2).

Based on a telecon with the NRC staff on September 22, 2004, supplemental information was requested with regard to the response to Item (1)(c) of the Bulletin. In response to the request, if circumferential cracking is observed in either the pressure boundary or non-pressure boundary portions of any locations covered under the scope of the Bulletin, FENOC will enter the issue into the BVPS Corrective Action Program, develop plans to perform an adequate extent-of-condition evaluation, and will discuss those plans with cognizant NRC technical staff prior to restarting the affected unit.

97/C)

I Beaver Valley Power Station, Unit No. I and No. 2 Supplemental Response to NRC Bulletin 2004-01 L-04-128 Page 2 No new commitments are contained in this submittal. If there are any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Compliance at 724-682-5284.

I declare under penalty of perjury that the foregoing is true and correct. Executed on September 21 , 2004.

Sincerely, L. William Pearce Attachments c: Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Sr. Resident Inspector Mr. S. J. Collins, NRC Region I Administrator