ML121240946
| ML121240946 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/15/2012 |
| From: | John Hughey Plant Licensing Branch 1 |
| To: | Joyce T Public Service Enterprise Group |
| Hughey J, NRR/DORL, 301-415-3204 | |
| References | |
| TAC ME7510 | |
| Download: ML121240946 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 15, 2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038
SUBJECT:
REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR SPRING 2011 REFUELING OUTAGE - SALEM NUCLEAR GENERATING STATION, UNIT NO.2 (TAC NO. ME7510)
Dear Mr. Joyce:
By letter dated October 24, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11305A046), PSEG Nuclear, LLC (PSEG) submitted a report summarizing the steam generator tube inspections performed at Salem Nuclear Generating Station, Unit No.2 (Salem Unit 2) during the spring 2011 refueling outage (2R18). This information was submitted in accordance with Salem Unit 2 Technical Specification (TS) 6.9.1.10. Additional information concerning these inspections was provided in PSEG's letter dated February 28,2011 (ADAMS Accession No. ML12088A010).
The Nuclear Regulatory Commission staff has completed its review of your submittals as documented in the enclosure. The staff concludes that PSEG has provided the information required by the TSs and that no additional follow-up is required at this time. This completes the NRC staff efforts for TAC No. ME7510.
If you have any questions regarding this matter, I may be reached at 301-415-3204.
- J20~
John D. Hughey, Project Manager Plant licensing Branch 1-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-311
Enclosure:
As stated cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
SUMMARY
OF THE OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF THE STEAM GENERATOR TUBE INSPECTION REPORT FOR THE 2R18 REFUELING OUTAGE IN SPRING 2011 SALEM NUCLEAR GENERATING STATION, UNIT NO.2 DOCKET NO. 50-311 By letters dated October 24, 2011, and February 28, 2012 (Agencywide Documents Access and Management Systems Accession Number ML11305A046 and ML12088A010), PSEG Nuclear, LLC (PSEG or the licensee) submitted information summarizing the results of the spring 2011 steam generator (SG) tube inspections at Salem Nuclear Generating Station, Unit No.2 (Salem Unit 2).
Salem Unit 2 has four AREVA Model 61/19T replacement SGs, each of which contains 5,048 U bend thermally treated Alloy 690 tubes. Each tube has a nominal outside diameter of 0.750 inches and a nominal wall thickness of 0.043 inches. During SG fabrication, the tubes were hydraulically expanded at both ends, over the full depth of the tubesheet. The tubesheet was drilled on a triangular pitch. The U-bends in rows 1 through 16 were stress relieved after bending. Eight stainless steel (Type 410) support plates, which have broached trefoil holes, provide lateral tube support to the vertical section of the tubes and three sets of stainless steel (Type 405M) anti-vibration bars support the U-bend section of the tubes.
The original Salem Unit 2 SGs were replaced during 2R16 and the second in-service inspections of the replacement SGs were conducted in 2R18.
The licensee provided the scope, extent, methods, and results of its SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the inspection findings.
Based on its review of the reports submitted, the NRC staff has the following observations and comments:
- The only service-induced indications detected were wear at the anti-vibration bars and tube support plates.
- None of the nuts/bolts/washers that were found loose in the 2R17 inspection were found loose, with the exception of the five inaccessible nuts that were evaluated in 2R17 and left as-is.
Enclosure
- 2
- Three of the five nuts left as-is in 2R 17 were able to be successfully tig htened to specification in 2R18. The licensee continues to investigate additional new/modified tooling to reach the remaining two nuts.
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by the technical specifications. In addition, the 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: C. Hunt Date: May 15, 2012
May 15,2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038 SUBJECT REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR SPRING 2011 REFUELING OUTAGE - SALEM NUCLEAR GENERATING STATION, UNIT NO.2 (TAC NO. ME7510)
Dear Mr. Joyce:
By letter dated October 24, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11305A046), PSEG Nuclear, LLC (PSEG) submitted a report summarizing the steam generator tube inspections performed at Salem Nuclear Generating Station, Unit No.2 (Salem Unit 2) during the spring 2011 refueling outage (2R 18). This information was submitted in accordance with Salem Unit 2 Technical Specification (TS) 6.9.1.10. Additional information concerning these inspections was provided in PSEG's letter dated February 28, 2011 (ADAMS Accession No. ML12088A010).
The Nuclear Regulatory Commission staff has completed its review of your submittals as documented in the enclosure. The staff concludes that PSEG has provided the information required by the TSs and that no additional follow-up is required at this time. This completes the NRC staff efforts for TAC No. ME7510.
If you have any questions regarding this matter, I may be reached at 301-415-3204.
Sincerely, IRAJ John D. Hughey, Project Manager Plant licenSing Branch 1-2 Division of Operating Reactor licenSing Office of Nuclear Reactor Regulation Docket No. 50-311
Enclosure:
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