ML070990172
| ML070990172 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/30/2007 |
| From: | Wang A NRC/NRR/ADRO/DORL/LPLIV |
| To: | Ridenoure R Omaha Public Power District |
| Wang A, NRR/DORL/LPLIV, 415-1445 | |
| References | |
| BL-04-001, TAC MC3480 | |
| Download: ML070990172 (4) | |
Text
April 30, 2007 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
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, RESPONSE FOR FORT CALHOUN STATION (TAC NO. MC3480)
Dear Mr. Ridenoure:
On May 28, 2004, the U.S. Nuclear Regulatory Commission (NRC) issued 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, to the industry. This bulletin informed addressees that current methods of inspecting the pressurizer penetrations and steam space piping connections fabricated from Alloy 82/182/600 materials may need to be supplemented with additional measures (e.g., bare-metal visual inspections) to detect pressurizer penetration and steam space piping connection flaws or leakage. The bulletin requested that addressees provide the NRC with information related to the materials of construction, the inspections that have been performed, and the inspections that will be performed to verify the integrity of the pressurizer penetrations and steam space piping connections.
By letter dated July 27, 2004, Omaha Public Power District (OPPD) provided its responses to items 1a, 1b, 1c, and 1d of Bulletin 2004-01 for the Fort Calhoun Station, Unit No. 1 (FCS).
OPPDs responses described its materials of fabrication and past, current, and future pressurizer penetrations and steam space piping inspection programs at FCS.
OPPDs response to item 1a reported that some of the materials used in the fabrication of the pressurizer penetrations and steam space piping connections were Alloy 82/182/600 materials.
This reply required you to provide further responses to the remaining items in the bulletin.
In response to item 1b, OPPD described prior inspections and inspection results of pressurizer penetrations and steam space piping connections, which had been performed at FCS. OPPDs response included the basis for concluding that FCS satisfies the applicable regulatory requirements related to the integrity of pressurizer penetrations and steam space piping connections.
In response to item 1c in the bulletin, OPPD provided a description of the Alloy 82/182/600 pressurizer penetration and steam space piping connection inspection program that will be implemented at your plant during the next and subsequent refueling outages. The description
R. T. Ridenoure included the items to be inspected; the percent coverage that would be performed at each location; the inspection methods to be used; the qualification standards for the inspection methods and personnel; the process used to resolve any inspection indications; the inspection documentation to be generated; and the basis for concluding that your plant will satisfy the applicable regulatory requirements related to the structural and leakage integrity of pressurizer penetrations and steam space piping connections. If leaking pressurizer penetrations or steam space piping connections are found, OPPD indicated that follow-up nondestructive examination (NDE) will be performed to characterize flaws in the leaking penetrations. OPPD provided its plans for expansion of the scope of NDE to be performed if circumferential flaws are found in any portion of the leaking pressurizer penetrations or steam space piping connections.
In response to item 1d in the bulletin, OPPD explained why the inspection program identified in the response to item 1c in the bulletin is adequate for the purpose of maintaining the integrity of the FCS reactor coolant pressure boundary and for meeting all applicable regulatory requirements, which pertain to your facility.
By letter dated July 27, 2005, OPPD provided a response to item 2a in Bulletin 2004-01. This letter provided a statement to the NRC indicating that the inspections described in your response to item 1c of the bulletin were completed during a recent FCS outage and a description of the as-found condition of the locations inspected was provided. OPPD also described any findings of relevant indications of through-wall leakage and follow-up NDE performed to characterize flaws in leaking penetrations or steam space piping connections. A summary of all relevant indications found by NDE, a summary of the disposition of any findings of boric acid, and a description of any corrective actions taken and/or repairs made as a result of the indications found was also provided in this letter.
The NRC staff has completed its activities associated with the review of OPPD's responses to Bulletin 2004-01 and finds OPPDs response to be acceptable. It should be noted that industry commitments or NRC staff regulatory actions may result in the need for you to modify your plans for the inspection and repair of items discussed in Bulletin 2004-01. For example, specific actions addressed in topical report MRP-139, "Materials Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guideline," and/or plant-specific Confirmatory Action Letters regarding dissimilar metal butt welds encompassed by Bulletin 2004-01 may exceed the scope of actions addressed in your response to Bulletin 2004-01. It is the NRC staffs expectation that you will revise your plan for the inspection and repair of items discussed in Bulletin 2004-01 consistent with other industry commitments or NRC staff regulatory actions. This closes the NRC staffs efforts with regard to the review of the Bulletin 2004-01 response for FCS. Please contact me at (301) 415-1445 if you have any questions on this issue.
Sincerely,
/RA/
Alan Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 cc: See next page
ML070990172 OFFICE NRR/LPL4/PM NRR/LPL4/LA DCI/CVIB/BC NRR/LPL4/BC NAME AWang LFeizollahi MMitchell THiltz DATE 04/30/07 04/26/07 4/24/07 04/30/07
April 2006 Ft. Calhoun Station, Unit 1 cc:
Winston & Strawn ATTN: James R. Curtiss, Esq.
1700 K Street, N.W.
Washington, DC 20006-3817 Chairman Washington County Board of Supervisors P.O. Box 466 Blair, NE 68008 Mr. John Hanna, Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007 Mr. David J. Bannister, Manager Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Joe L. McManis Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Daniel K. McGhee Bureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319