ML071580140
| ML071580140 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/18/2007 |
| From: | Stewart Bailey NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | Young D Progress Energy Florida |
| Bailey S , NRR/ADRO/DORL, 415-1321 | |
| References | |
| BL-04-001, TAC MC3472 | |
| Download: ML071580140 (5) | |
Text
June 18, 2007 Mr. Dale E. Young, Vice President Crystal River Nuclear Plant (NA1B)
ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708
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 CRYSTAL RIVER, UNIT 3 (TAC NO. MC3472)
Dear Mr. Young:
On May 28, 2004, the U.S. Nuclear Regulatory Commission (NRC) issued Bulletin (B) 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.
The Florida Power Corporation (the licensee) provided its responses to B 2004-01 for Crystal River, Unit No. 3 (CR-3), by letters dated July 26, 2004, February 7, 2006, and September 18, 2006.
The licensees responses to B 2004-01 items 1a, 1b, 1c, and 1d were provided by letter dated July 26, 2004, as supplemented by letter dated September 18, 2006. The licensees responses described the materials of fabrication and past, current, and future pressurizer penetrations, as well as steam space piping inspection programs at CR-3.
The licensees 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.
In response to item 1b, the licensee described prior inspections and inspection results of pressurizer penetrations and steam space piping connections that had been performed at CR-3. The licensees response included the basis for concluding that CR-3 satisfies the applicable regulatory requirements related to the integrity of pressurizer penetrations and steam space piping connections.
In response to item 1c, the licensee provided a description of the Alloy 82/182/600 pressurizer penetration and steam space piping connection inspection program that will be implemented at CR-3 during the next and subsequent refueling outages. The description included the items to be inspected, the percentage of 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
D. Young to be generated, and the basis for concluding that CR-3 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, the licensee indicated that follow-up nondestructive examination (NDE) will be performed to characterize flaws in the leaking penetrations. The licensee 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, the licensee explained why the inspection program identified in the response to item 1c is adequate for the purpose of maintaining the integrity of the CR-3 reactor coolant pressure boundary and for meeting all applicable regulatory requirements that pertain to CR-3.
The licensees response to B 2004-01 item 2a was provided by letter dated February 7, 2006, as supplemented by letter dated September 18, 2006. The licensee stated that the inspections described in the response to item 1c were completed during a recent CR-3 outage and described the as-found condition of the locations inspected. The licensee 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 were also provided.
The NRC staff has completed its activities associated with the review of the licensee's responses to B 2004-01 and finds the licensee's responses to be acceptable. It should be noted that industry commitments or staff regulatory actions may result in the need for the licensee to modify its plans for the inspection and repair of items discussed in B 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 B 2004-01 may exceed the scope of actions addressed in the licensees response to B 2004-01. It is the staffs expectation that the licensee will revise the plans for the inspection and repair of items discussed in B 2004-01 consistent with other industry commitments or staff regulatory actions.
This closes the staffs efforts with regard to the review of the B 2004-01 response for CR-3.
Please contact me at 301-415-1321 if you have any questions on this issue.
Sincerely,
/RA/
Stewart N. Bailey, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302 cc: See next page
D. Young June 18, 2007 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 CR-3 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, the licensee indicated that follow-up nondestructive examination (NDE) will be performed to characterize flaws in the leaking penetrations. The licensee 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, the licensee explained why the inspection program identified in the response to item 1c is adequate for the purpose of maintaining the integrity of the CR-3 reactor coolant pressure boundary and for meeting all applicable regulatory requirements that pertain to CR-3.
The licensees response to B 2004-01 item 2a was provided by letter dated February 7, 2006, as supplemented by letter dated September 18, 2006. The licensee stated that the inspections described in the response to item 1c were completed during a recent CR-3 outage and described the as-found condition of the locations inspected. The licensee 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 were also provided.
The NRC staff has completed its activities associated with the review of the licensee's responses to B 2004-01 and finds the licensee's responses to be acceptable. It should be noted that industry commitments or staff regulatory actions may result in the need for the licensee to modify its plans for the inspection and repair of items discussed in B 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 B 2004-01 may exceed the scope of actions addressed in the licensees response to B 2004-01. It is the staffs expectation that the licensee will revise the plans for the inspection and repair of items discussed in B 2004-01 consistent with other industry commitments or staff regulatory actions.
This closes the staffs efforts with regard to the review of the B 2004-01 response for CR-3.
Please contact me at 301-415-1321 if you have any questions on this issue.
Sincerely,
/RA/
Stewart N. Bailey, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302 cc: See next page Distribution: RidsAcrsAcnwMailCenter RidsNrrLABClayton RidsNrrPMSBailey PUBLIC RidsNrrDorlLpl2-2 RidsOgcRp RidsRgn2MailCenter EAndruszkiewicz RidsNrrDciCvib JO'Driscoll LPL2-2 R/F ADAMS ACCESSION NUMBER: ML071580140 OFFICE LPL2-2/PM LPL2-2/LA CVIB/BC LPL2-2/BC NAME SBailey BClayton MMitchell TBoyce DATE 06/18/07 06/14/07 06/18/07 06/18/07
D. Young OFFICIAL RECORD COPY
Mr. Dale E. Young Crystal River Nuclear Plant, Unit 3 Florida Power Corporation cc:
Mr. R. Alexander Glenn Chairman Associate General Counsel (MAC-BT15A) Board of County Commissioners Florida Power Corporation Citrus County P.O. Box 14042 110 North Apopka Avenue St. Petersburg, Florida 33733-4042 Inverness, Florida 34450-4245 Mr. Jon A. Franke Mr. Michael J. Annacone Plant General Manager Engineering Manager Crystal River Nuclear Plant (NA2C) Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 Mr. Jim Mallay Mr. Daniel L. Roderick Framatome ANP Director Site Operations 1911 North Ft. Myer Drive, Suite 705 Crystal River Nuclear Plant (NA2C)
Rosslyn, Virginia 22209 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. William A. Passetti, Chief Department of Health Senior Resident Inspector Bureau of Radiation Control Crystal River Unit 3 2020 Capital Circle, SE, Bin #C21 U.S. Nuclear Regulatory Commission Tallahassee, Florida 32399-1741 6745 N. Tallahassee Road Crystal River, Florida 34428 Attorney General Department of Legal Affairs Mr. Terry D. Hobbs The Capitol Manager, Nuclear Assessment Tallahassee, Florida 32304 Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Mr. Craig Fugate, Director Crystal River, Florida 34428-6708 Division of Emergency Preparedness Department of Community Affairs David T. Conley 2740 Centerview Drive Associate General Counsel II - Legal Dept.
Tallahassee, Florida 32399-2100 Progress Energy Service Company, LLC Post Office Box 1551 Raleigh, North Carolina 27602-1551