Letter Sequence Approval |
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TAC:MD4807, Steam Generator Tube Integrity (Approved, Closed) |
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Text
October 29, 2007 Mr. William Levis President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORTS FOR FALL 2006 - SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 (TAC NO. MD4807)
Dear Mr. Levis:
By letters dated November 6, 2006, and March 1, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML063190294 and ML070720424, respectively), PSEG Nuclear LLC (PSEG) submitted reports summarizing the steam generator tube inspections performed at Salem Nuclear Generating Station, Unit No. 2 (Salem Unit 2) during the fall 2006 refueling outage (2R15). This information was submitted in accordance with Salem Unit 2 Technical Specifications (TSs) 4.4.6.5.a and 6.9.1.5.b. Additional information concerning these inspections was summarized by the Nuclear Regulatory Commission (NRC) staff in a letter dated May 10, 2007, and in PSEGs letter dated August 3, 2007 (ADAMS Accession Nos. ML071310308 and ML072270069, respectively).
As discussed in the enclosed evaluation, the NRC staff concludes that PSEG provided the information required by the Salem Unit 2 TSs. In addition, the NRC staff did not identify any technical issues that warrant follow-up action at this time. This completes the NRC staff efforts for TAC No. MD4807.
If you have any questions regarding this matter, I may be reached at 301-415-1420.
Sincerely,
/RA/
Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-311
Enclosure:
Evaluation cc w/encl: See next page
Mr. William Levis President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORTS FOR FALL 2006 - SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 (TAC NO. MD4807)
Dear Mr. Levis:
By letters dated November 6, 2006, and March 1, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML063190294 and ML070720424, respectively), PSEG Nuclear LLC (PSEG) submitted reports summarizing the steam generator tube inspections performed at Salem Nuclear Generating Station, Unit No. 2 (Salem Unit 2) during the fall 2006 refueling outage (2R15). This information was submitted in accordance with Salem Unit 2 Technical Specifications (TSs) 4.4.6.5.a and 6.9.1.5.b. Additional information concerning these inspections was summarized by the Nuclear Regulatory Commission (NRC) staff in a letter dated May 10, 2007, and in PSEGs letter dated August 3, 2007 (ADAMS Accession Nos. ML071310308 and ML072270069, respectively).
As discussed in the enclosed evaluation, the NRC staff concludes that PSEG provided the information required by the Salem Unit 2 TSs. In addition, the NRC staff did not identify any technical issues that warrant follow-up action at this time. This completes the NRC staff efforts for TAC No. MD4807.
If you have any questions regarding this matter, I may be reached at 301-415-1420.
Sincerely,
/RA/
Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-311
Enclosure:
Evaluation cc w/encl: See next page DISTRIBUTION:
PUBLIC RidsAcrsAcnwMailCenter LPL1-2 Reading RidsRgn1MailCenter RidsNrrDorlLpl1-2 AHiser RidsNrrLAABaxter KKarwoski RidsNrrPMREnnis LMiller RidsOgcRp ADAMS Accession No.: ML072830347 *By memo dated 8/30/07 OFFICE LPL1-2/PM LPL 1-2/LA CSGB/BC LPL1-2/BC NAME REnnis ABaxter AHiser HChernoff DATE 10/10/07 10/11/07 8/30/07 10/29/07
OFFICIAL RECORD COPY Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:
Mr. Thomas Joyce Township Clerk Senior Vice President - Operations Lower Alloways Creek Township PSEG Nuclear Municipal Building, P.O. Box 157 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Paul Bauldauf, P.E., Asst. Director Mr. Dennis Winchester Radiation Protection Programs Vice President - Nuclear Assessment NJ Department of Environmental PSEG Nuclear Protection and Energy P.O. Box 236 CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. Robert Braun Mr. Brian Beam Site Vice President - Salem Board of Public Utilities PSEG Nuclear 2 Gateway Center, Tenth Floor P.O. Box 236 Newark, NJ 07102 Hancocks Bridge, NJ 08038 Regional Administrator, Region I Mr. Carl Fricker U.S. Nuclear Regulatory Commission Vice President - Operations Support 475 Allendale Road PSEG Nuclear King of Prussia, PA 19406 P.O. Box 236 Hancocks Bridge, NJ 08038 Senior Resident Inspector Salem Nuclear Generating Station Mr. George Gellrich U.S. Nuclear Regulatory Commission Plant Manager - Salem Drawer 0509 PSEG Nuclear Hancocks Bridge, NJ 08038 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. James Mallon Manager - Licensing PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Steven Mannon Manager - Salem Regulatory Assurance PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038
EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION STEAM GENERATOR TUBE INSPECTION REPORTS FOR FALL 2006 SALEM NUCLEAR GENERATING STATION, UNIT NO 2 DOCKET NO. 50-311
1.0 INTRODUCTION
By letters dated November 6, 2006, and March 1, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML063190294 and ML070720424, respectively), PSEG Nuclear LLC (the licensee) submitted reports summarizing the steam generator (SG) tube inspections performed at Salem Nuclear Generating Station, Unit No. 2 (Salem Unit 2) during the fall 2006 refueling outage (2R15). This information was submitted in accordance with Salem Unit 2 Technical Specifications (TSs) 4.4.6.5.a and 6.9.1.5.b. Additional information concerning these inspections was summarized by the Nuclear Regulatory Commission (NRC) staff in a letter dated May 10, 2007, and in PSEGs letter dated August 3, 2007 (ADAMS Accession Nos. ML071310308 and ML072270069, respectively).
2.0 BACKGROUND
Salem Unit 2 has four Westinghouse model 51 SGs. Each SG contains approximately 3,400 mill-annealed Alloy 600 tubes. Each tube has a nominal outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches. The tubes were explosively expanded at both ends for the full-length of the tubesheet and are supported by a number of carbon steel tube supports with round shaped holes. The hot-leg temperature is approximately 595 °F.
3.0 EVALUATION The licensee provided the scope, extent, methods, and results of their SG tube inspections in the documents referenced above. The licensee also described corrective actions in the form of tube plugging and tube stabilization taken in response to the inspection findings.
Based on review of the information submitted by the licensee, the NRC staff has the following observations/comments:
- 1. The licensee indicated that the anti-vibration bar wear and cold-leg thinning (CLT) identified during 2R15 is relatively consistent with prior experience at Salem Unit 2; however, the 95th percentile growth rate for the CLT indications increased from 7-percent through-wall (TW) per Effective Full Power Years (EFPY) in 2R14 to 13-percent TW per EFPY in 2R15. In addition, the licensee reported that these wear indications satisfied the structural integrity performance criteria.
Enclosure
- 2. The SGs at Salem Unit 2 are scheduled to be replaced in the spring of 2008.
- 3. The licensees dent and ding examinations were focused on the hot-leg. Recently, a plant detected crack-like indications at cold-leg dings prior to observing crack-like indications at hot-leg dings.
4.0 CONCLUSION
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by the Salem Unit 2 TSs. In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Principal Contributor: L. S. Miller Date: October 29, 2007
