ML051310400

Request for Additional Information

ML051310400
Person / Time
Site:	Catawba
Issue date:	05/11/2005
From:	Sean Peters NRC/NRR/DLPM/LPD2
To:	Jamil D Duke Energy Corp
Peters S, NRR/DLPM, 415-1842
References
TAC MC4993
Download: ML051310400 (6)

Text

May 11, 2005 Mr. D. M. Jamil Vice President Catawba Nuclear Station Duke Energy Corporation 4800 Concord Road York, SC 29745

SUBJECT:

CATAWBA NUCLEAR STATION, UNIT 2 RE: REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC4993)

Dear Mr. Jamil:

By letters dated October 19 and December 2, 2004, Duke Energy Corporation submitted for Nuclear Regulatory Commission (NRC) staff review, an evaluation of a flaw indication in the reactor coolant hot leg to steam generator nozzle connection, that was discovered on October 7, 2004, during the 13th refueling outage for Catawba Nuclear Station, Unit 2. The NRC staff has reviewed the submittals and has determined that additional information is required, as identified in the Enclosure.

We discussed these issues with your staff on May 5, 2005. Your staff indicated that you would attempt to provide your response by June 30, 2005.

Please contact me at (301) 415-1842, if you have any questions on these issues.

Sincerely,

/RA/

Sean E. Peters, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-414

Enclosure:

As stated cc w/encl: See next page

May 11, 2005 Mr. D. M. Jamil Vice President Catawba Nuclear Station Duke Energy Corporation 4800 Concord Road York, SC 29745

SUBJECT:

CATAWBA NUCLEAR STATION, UNIT 2 RE: REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC4993)

Dear Mr. Jamil:

By letters dated October 19 and December 2, 2004, Duke Energy Corporation submitted for Nuclear Regulatory Commission (NRC) staff review, an evaluation of a flaw indication in the reactor coolant hot leg to steam generator nozzle connection, that was discovered on October 7, 2004, during the 13th refueling outage for Catawba Nuclear Station, Unit 2. The NRC staff has reviewed the submittals and has determined that additional information is required, as identified in the Enclosure.

We discussed these issues with your staff on May 5, 2005. Your staff indicated that you would attempt to provide your response by June 30, 2005.

Please contact me at (301) 415-1842, if you have any questions on these issues.

Sincerely,

/RA/

Sean E. Peters, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-414

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION:

PUBLIC OGC SSheng PDII-1 R/F ACRS SPeters EMarinos LPlisco, RII CHawes ADAMS Accession: ML051310400 NRR-088 OFFICE PDII-1/PM PDII-1/LA PDII-1/SC NAME SPeters CHawes JNakoski DATE 05/10/05 05/10/05 05/11/05 OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATION DUKE POWER COMPANY CATAWBA NUCLEAR STATION, UNIT 2 DOCKET NO. 50-414 The Nuclear Regulatory Commission (NRC) staff has reviewed the licensees submittals dated October 19 and December 2, 2004, regarding an evaluation of a flaw indication in the reactor coolant hot leg to steam generator nozzle connection, that was discovered on October 7, 2004, during the 13th refueling outage for Catawba Nuclear Station, Unit 2. The NRC staff has identified the following information that is needed to enable the continuation of its review.

1. In the letter dated October 19, 2004, you stated, [t]he indication was located near the interface between the safe-end and field weld at the bottom of the nozzle. Please confirm whether the flaw indication is in the safe end or in the field weld.

2. In the letter dated October 19, 2004, you stated, [t]his letter submits the fracture mechanics analysis to the NRC (see attachment). The NRC staff did not find in your submittal an evaluation of the detected flaw indication (1 inch long circumferential embedded flaw, 1.01 inches from the outside diameter of the pipe) using WCAP-15658-P, Revision 1. Please provide this information. The response should include the WCAP figure number (Figure A-4.6, Figure A-4.7, Figure A-4.8, or Figure A-4.9) that you used for evaluation of the detected flaw in the steam generator primary nozzle weld region. The response should also include the depth of the detected flaw (the size of the flaw in the wall thickness direction).

3. On Page 3-1 of WCAP-15658-P, Revision 1, Flaw Evaluation Handbook for Catawba Unit 2 Steam Generator Primary Nozzle Weld Regions, November 2004, it is stated, [t]he stress intensity factor calculation for an embedded flaw was taken from the work by Shah and Kobayashi [6] which is applicable to an embedded flaw in an infinite medium....This expression has been shown to be applicable to embedded flaws in a thick-walled pressure vessel in a paper by Lee and Bamford [7]. Please demonstrate the applicability of Kobayashis formulas for embedded flaws to your current application by addressing (1) the difference between the finite geometry of the current application and an infinite medium discussed in Kobayashis paper, and (2) the difference between the ratio of plate thickness to crack depth, t/2a, of the current application and that discussed in Kobayashis paper. Provide Reference 7 of WCAP-15658-P, Revision 1 (Paper 83-PVP-92 by Lee and Bamford) if you believe it would help your explanation.

4. On Page 3-4 of WCAP-15658-P, Revision 1, it is stated, NRC procedures exist for addressing the impact of thermal aging on fracture toughness for full-service life. The approved procedures were applied to the nozzle safe end to pipe weld, as well as to the cast piping itself.

Provide the specific document (e.g., NUREG number) and parameters used (e.g., ferrite content) in your determination of fracture toughness for full-service life using NRC procedures.

Explain how you use these NRC procedures to determine the first set of proprietary JIc and Tmat given on Page 3-4. It is further stated on this page, [e]ven with thermal aging, equivalent to full service for SAW welds, the tearing modulus remains high (>100) and the unaged toughness, JIc, is not significantly reduced. Provide information supporting this statement.

Catawba Nuclear Station, Unit 2 cc:

Mr. Lee Keller, Manager Mr. Henry Porter, Assistant Director Regulatory Compliance Division of Waste Management Duke Energy Corporation Bureau of Land and Waste Management 4800 Concord Road Dept. of Health and Environmental Control York, South Carolina 29745 2600 Bull Street Columbia, South Carolina 29201-1708 Ms. Lisa F. Vaughn Duke Energy Corporation Mr. R.L. Gill, Jr., Manager Mail Code - PB05E Nuclear Regulatory Issues 422 South Church Street and Industry Affairs P.O. Box 1244 Duke Energy Corporation Charlotte, North Carolina 28201-1244 526 South Church Street Mail Stop EC05P Ms. Anne Cottingham, Esquire Charlotte, North Carolina 28202 Winston and Strawn LLP 1700 L Street, NW Saluda River Electric Washington, DC 20006 P.O. Box 929 Laurens, South Carolina 29360 North Carolina Municipal Power Agency Number 1 Mr. Peter R. Harden, IV, Vice President 1427 Meadowwood Boulevard Customer Relations and Sales P.O. Box 29513 Westinghouse Electric Company Raleigh, North Carolina 27626 6000 Fairview Road 12th Floor County Manager of York County Charlotte, North Carolina 28210 York County Courthouse York, South Carolina 29745 Mr. T. Richard Puryear Owners Group (NCEMC)

Piedmont Municipal Power Agency Duke Energy Corporation 121 Village Drive 4800 Concord Road Greer, South Carolina 29651 York, South Carolina 29745 Ms. Karen E. Long Mr. Richard M. Fry, Director Assistant Attorney General Division of Radiation Protection North Carolina Department of Justice NC Dept. of Environment, Health, P.O. Box 629 and Natural Resources Raleigh, North Carolina 27602 3825 Barrett Drive Raleigh, North Carolina 27609-7721 NCEM REP Program Manager 4713 Mail Service Center Mr. Henry Barron Raleigh, North Carolina 27699-4713 Group Vice President, Nuclear Generation and Chief Nuclear Officer North Carolina Electric Membership Corp. P.O. Box 1006-EC07H P.O. Box 27306 Charlotte, NC 28201-1006 Raleigh, North Carolina 27611 Diane Curran Senior Resident Inspector Harmon, Curran, Spielbergy &

U.S. Nuclear Regulatory Commission Eisenberg, LLP 4830 Concord Road 1726 M Street, NW York, South Carolina 29745 Suite 600 Washington, DC 20036