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| | number = ML14070A254 | | | number = ML14070A254 |
| | issue date = 03/26/2014 | | | issue date = 03/26/2014 |
| | title = Salem Nuclear Generating Station, Unit 2 - Review of the Fall 2012 Steam Generator Tube Inservice Inspections During Refueling Outage 2R19 (TAC No. MF1783) | | | title = Review of the Fall 2012 Steam Generator Tube Inservice Inspections During Refueling Outage 2R19 |
| | author name = Hughey J D | | | author name = Hughey J |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = Joyce T | | | addressee name = Joyce T |
| Line 9: |
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| | docket = 05000311 | | | docket = 05000311 |
| | license number = DPR-075 | | | license number = DPR-075 |
| | contact person = Hughey J D, NRR/DORL, 415-3204 | | | contact person = Hughey J, NRR/DORL, 415-3204 |
| | case reference number = TAC MF1783 | | | case reference number = TAC MF1783 |
| | document type = Inservice/Preservice Inspection and Test Report, Letter | | | document type = Inservice/Preservice Inspection and Test Report, Letter |
| | page count = 4 | | | page count = 4 |
| | project = TAC:MF1783 | | | project = TAC:MF1783 |
| | stage = | | | stage = Approval |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038 March 26, 2014 SUBJECT: SALEM NUCLEAR GENERATING STATION, UNIT 2-REVIEW OF THE FALL 2012 STEAM GENERATOR TUBE INSERVICE INSPECTIONS DURING REFUELING OUTAGE 2R19 (TAC NO. MF1783) Dear Mr. Joyce: By letter dated May 9, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13133A083), as supplemented by letter dated January 10, 2014 (ADAMS Accession No. ML 14010A428), PSEG Nuclear LLC (PSEG) submitted information summarizing the results of their fall 2012 steam generator (SG) tube inspections performed during the 19th refueling outage 2R 19 at Salem Nuclear Generating Station, Unit 2 (Salem 2). In addition to these reports, the Nuclear Regulatory Commission (NRC) staff summarized a conference call held with PSEG, concerning the 2012 SG tube inspections, in a letter dated May 10, 2013 (ADAMS Accession No. ML 13109A235). The NRC 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 Salem 2 technical specifications and that no additional follow-up is required at this time. This completes the NRC staff efforts for Technical Assignment Control (TAC) No. MF1783. If you have any questions regarding this matter, I may be reached at 301-415-3204 or at John. Hughey@nrc.gov. Docket No. 50-311 Enclosure: Review of 2012 SG Tube Inspections cc w/encl: Distribution via Listserv Sincerely, John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 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 2R19 REFUELING OUTAGE IN FALL 2012 SALEM NUCLEAR GENERATING STATION, UNIT 2 DOCKET NO. 50-311 By letter dated May 9, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13133A083), as supplemented by letter dated January 10, 2014 (ADAMS Accession No. ML 1401 OA428), PSEG Nuclear LLC (PSEG or the licensee) submitted information summarizing the results of their fall 2012 steam generator (SG) tube inspections performed during refueling outage 2R19 at Salem Nuclear Generating Station, Unit 2 (Salem 2). Salem 2 has four AREVA Modei61/19T SGs, each of which contains 5,048 U-bend 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. PSEG provided the scope, extent, methods and results of their SG tube inspections in the submittals referenced above. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings. The tubes in all four SGs were inspected during the 2R 19 refueling outage in the fall of 2012. After reviewing the information provided by PSEG, the NRC staff has the following comments/observations: | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 26, 2014 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038 |
| | |
| | ==SUBJECT:== |
| | SALEM NUCLEAR GENERATING STATION, UNIT 2- REVIEW OF THE FALL 2012 STEAM GENERATOR TUBE INSERVICE INSPECTIONS DURING REFUELING OUTAGE 2R19 (TAC NO. MF1783) |
| | |
| | ==Dear Mr. Joyce:== |
| | |
| | By letter dated May 9, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13133A083), as supplemented by letter dated January 10, 2014 (ADAMS Accession No. ML14010A428), PSEG Nuclear LLC (PSEG) submitted information summarizing the results of their fall 2012 steam generator (SG) tube inspections performed during the 19th refueling outage 2R 19 at Salem Nuclear Generating Station, Unit 2 (Salem 2). In addition to these reports, the Nuclear Regulatory Commission (NRC) staff summarized a conference call held with PSEG, concerning the 2012 SG tube inspections, in a letter dated May 10, 2013 (ADAMS Accession No. ML13109A235). |
| | The NRC 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 Salem 2 technical specifications and that no additional follow-up is required at this time. This completes the NRC staff efforts for Technical Assignment Control (TAC) No. MF1783. |
| | If you have any questions regarding this matter, I may be reached at 301-415-3204 or at John. Hughey@nrc.gov. |
| | Sincerely, 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:== |
| | |
| | Review of 2012 SG Tube Inspections 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 2R19 REFUELING OUTAGE IN FALL 2012 SALEM NUCLEAR GENERATING STATION, UNIT 2 DOCKET NO. 50-311 By letter dated May 9, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13133A083), as supplemented by letter dated January 10, 2014 (ADAMS Accession No. ML 1401 OA428), PSEG Nuclear LLC (PSEG or the licensee) submitted information summarizing the results of their fall 2012 steam generator (SG) tube inspections performed during refueling outage 2R19 at Salem Nuclear Generating Station, Unit 2 (Salem 2). |
| | Salem 2 has four AREVA Modei61/19T 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. |
| | PSEG provided the scope, extent, methods and results of their SG tube inspections in the submittals referenced above. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings. The tubes in all four SGs were inspected during the 2R 19 refueling outage in the fall of 2012. |
| | After reviewing the information provided by PSEG, the NRC staff has the following comments/observations: |
| * As of the 2R 19 outage, the SGs had operated for approximately 50 effective full-power months. | | * As of the 2R 19 outage, the SGs had operated for approximately 50 effective full-power months. |
| * There are two inaccessible nuts on secondary side components (hatches, camera ports). Other nuts on these components were identified as being loose in a prior inspection. The licensee stated that it is investigating additional new/modified tooling for the two inaccessible nuts. | | * There are two inaccessible nuts on secondary side components (hatches, camera ports). Other nuts on these components were identified as being loose in a prior inspection. The licensee stated that it is investigating additional new/modified tooling for the two inaccessible nuts. |
| * In 3 of the 4 SGs, wear was identified at a tube support plate in the tube located in row 1, column 63. Although wear at the tube support plates normally tends to be random, Enclosure | | * In 3 of the 4 SGs, wear was identified at a tube support plate in the tube located in row 1, column 63. Although wear at the tube support plates normally tends to be random, Enclosure |
| -2-the licensee did not identify any unique cause related to the wear observed on these specific tubes. Only 19 tubes were identified with wear at the tube support plates in all four SGs. The licensee plans to inspect these tubes during the next refueling outage. Based on the review of the information provided, the NRC staff concludes that PSEG provided the information required by the Salem 2 technical specifications. 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: A. Obodoako Date: March 26, 2014 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038 March 26, 2014 SUBJECT: SALEM NUCLEAR GENERATING STATION, UNIT 2-REVIEW OF THE FALL 2012 STEAM GENERATOR TUBE INSERVICE INSPECTIONS DURING REFUELING OUTAGE 2R19 (TAC NO. MF1783) Dear Mr. Joyce: By letter dated May 9, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13133A083), as supplemented by letter dated January 10, 2014 (ADAMS Accession No. ML 14010A428), PSEG Nuclear LLC (PSEG) submitted information summarizing the results of their fall 2012 steam generator (SG) tube inspections performed during the 19th refueling outage 2R19 at Salem Nuclear Generating Station, Unit 2 (Salem 2). In addition to these reports, the Nuclear Regulatory Commission (NRC) staff summarized a conference call held with PSEG, concerning the 2012 SG tube inspections, in a letter dated May 10, 2013 (ADAMS Accession No. ML 13109A235). The NRC 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 Salem 2 technical specifications and that no additional follow-up is required at this time. This completes the NRC staff efforts for Technical Assignment Control (TAC) No. MF1783. If you have any questions regarding this matter, I may be reached at 301-415-3204 or at John. Hughey@nrc.gov. Docket No. 50-311 Enclosure: Sincerely, Ira/ John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Review of 2012 SG Tube Inspections cc w/encl: Distribution via Listserv DISTRIBUTION: Public LPL1-2 R/F RidsNrrDorllpl1-2 Resource RidsNrrLAABaxter Resource RidsNrrPMSalem Resource KKarwoski, NRR/DE RidsRgn1 MailCenter Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDeEsgb Resource A DA S M Accession No.: M 1 L 4070A254 OFFICE NRR/LPL 1-2/PM NRR/LPL 1-2/LAit LPL1-2/LA NAME JHughey KBeckford A Baxter DATE 03/26//2014 3/25/2014 03/26//2014 OFFICIAL RECORD COPY AObodoako, NRR/DE GKulesa, NRR/DE MGray, Rl *by memo dated ESGB/BC* LPL1-2/BC GKluesa MKhanna 02/12/2014 03/26//2014
| | |
| }} | | the licensee did not identify any unique cause related to the wear observed on these specific tubes. Only 19 tubes were identified with wear at the tube support plates in all four SGs. The licensee plans to inspect these tubes during the next refueling outage. |
| | Based on the review of the information provided, the NRC staff concludes that PSEG provided the information required by the Salem 2 technical specifications. 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: A. Obodoako Date: March 26, 2014 |
| | |
| | ML14010A428), PSEG Nuclear LLC (PSEG) submitted information summarizing the results of their fall 2012 steam generator (SG) tube inspections performed during the 19th refueling outage 2R19 at Salem Nuclear Generating Station, Unit 2 (Salem 2). In addition to these reports, the Nuclear Regulatory Commission (NRC) staff summarized a conference call held with PSEG, concerning the 2012 SG tube inspections, in a letter dated May 10, 2013 (ADAMS Accession No. ML13109A235). |
| | The NRC 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 Salem 2 technical specifications and that no additional follow-up is required at this time. This completes the NRC staff efforts for Technical Assignment Control (TAC) No. MF1783. |
| | If you have any questions regarding this matter, I may be reached at 301-415-3204 or at John. Hughey@nrc.gov. |
| | Sincerely, Ira/ |
| | 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:== |
| | |
| | Review of 2012 SG Tube Inspections cc w/encl: Distribution via Listserv DISTRIBUTION: |
| | Public KKarwoski, NRR/DE LPL1-2 R/F RidsRgn1 MailCenter Resource AObodoako, NRR/DE RidsNrrDorllpl1-2 Resource RidsAcrsAcnw_MailCTR Resource GKulesa, NRR/DE RidsNrrLAABaxter Resource RidsNrrDeEsgb Resource MGray, Rl RidsNrrPMSalem Resource ADAMS Accession No.: ML14070A254 *by memo dated OFFICE NRR/LPL 1-2/PM NRR/LPL 1-2/LAit LPL1-2/LA ESGB/BC* LPL1-2/BC NAME JHughey KBeckford ABaxter GKluesa MKhanna DATE 03/26//2014 3/25/2014 03/26//2014 02/12/2014 03/26//2014}} |
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LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024
Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary
LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024
Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary
IR 05000272/20240112024-04-0101 April 2024
And Salem Nuclear Generating Station, Units 1 and 2 - Plant Modification and Annual Problem Identification and Resolution Inspection Report 05000354/2024011, 05000272/2024011, and 05000311/2024011
LR-N24-0028, And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024
And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal
LR-N24-0021, And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2024-03-20020 March 2024
And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums
IR 05000272/20244032024-03-20020 March 2024
And Hope Creek Generating Station - Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000272/2024403, 05000311/2024403, and 05000354/2024403
ML24071A2132024-03-12012 March 2024
Senior Reactor and Reactor Operator Initial License Examinations
LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024
Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report
LR-N24-0022, Spent Fuel Cask Registration2024-02-29029 February 2024
Spent Fuel Cask Registration
IR 05000272/20230062024-02-28028 February 2024
Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023006 and 05000311/2023006
IR 05000272/20244012024-02-26026 February 2024
And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024401, 05000272/2024401 and 05000311/2024401 (Cover Letter Only)
LR-N24-0009, In-Service Inspection Activities2024-02-0505 February 2024
In-Service Inspection Activities
IR 05000272/20230042024-02-0505 February 2024
Integrated Inspection Report 05000272/2023004 and 05000311/2023004
ML24009A1022024-01-26026 January 2024
– Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
IR 05000272/20234012024-01-22022 January 2024
Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401
ML24004A1542024-01-0808 January 2024
Notification of Conduct of a Fire Protection Team Inspection
LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023
Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days
ML23270C0072023-11-29029 November 2023
Notice of Proposed Amendment to Decommissioning Trust Agreement
LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023
Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion
ML23324A3072023-11-17017 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML24250A0582023-11-14014 November 2023
PSEG to Marine Mammal Stranding Center, Salem Sea Turtle Stranding Response Services
IR 05000272/20230032023-11-13013 November 2023
Integrated Inspection Report 05000272/2023003 and 05000311/2023003
LR-N23-0072, Core Operating Limits Report – Cycle 302023-11-0101 November 2023
Core Operating Limits Report – Cycle 30
IR 05000272/20230102023-10-12012 October 2023
Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010
IR 05000272/20234022023-10-12012 October 2023
And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only)
LR-N23-0045, And Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023
And Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement
ML23249A2612023-09-0606 September 2023
License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary
IR 05000272/20230052023-08-31031 August 2023
Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005)
ML23233A0762023-08-21021 August 2023
Requalification Program Inspection
ML23192A8212023-08-14014 August 2023
And Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location
2024-09-23
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 26, 2014 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT 2- REVIEW OF THE FALL 2012 STEAM GENERATOR TUBE INSERVICE INSPECTIONS DURING REFUELING OUTAGE 2R19 (TAC NO. MF1783)
Dear Mr. Joyce:
By letter dated May 9, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13133A083), as supplemented by letter dated January 10, 2014 (ADAMS Accession No. ML14010A428), PSEG Nuclear LLC (PSEG) submitted information summarizing the results of their fall 2012 steam generator (SG) tube inspections performed during the 19th refueling outage 2R 19 at Salem Nuclear Generating Station, Unit 2 (Salem 2). In addition to these reports, the Nuclear Regulatory Commission (NRC) staff summarized a conference call held with PSEG, concerning the 2012 SG tube inspections, in a letter dated May 10, 2013 (ADAMS Accession No. ML13109A235).
The NRC 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 Salem 2 technical specifications and that no additional follow-up is required at this time. This completes the NRC staff efforts for Technical Assignment Control (TAC) No. MF1783.
If you have any questions regarding this matter, I may be reached at 301-415-3204 or at John. Hughey@nrc.gov.
Sincerely, 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:
Review of 2012 SG Tube Inspections 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 2R19 REFUELING OUTAGE IN FALL 2012 SALEM NUCLEAR GENERATING STATION, UNIT 2 DOCKET NO. 50-311 By letter dated May 9, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13133A083), as supplemented by letter dated January 10, 2014 (ADAMS Accession No. ML 1401 OA428), PSEG Nuclear LLC (PSEG or the licensee) submitted information summarizing the results of their fall 2012 steam generator (SG) tube inspections performed during refueling outage 2R19 at Salem Nuclear Generating Station, Unit 2 (Salem 2).
Salem 2 has four AREVA Modei61/19T 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.
PSEG provided the scope, extent, methods and results of their SG tube inspections in the submittals referenced above. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings. The tubes in all four SGs were inspected during the 2R 19 refueling outage in the fall of 2012.
After reviewing the information provided by PSEG, the NRC staff has the following comments/observations:
- As of the 2R 19 outage, the SGs had operated for approximately 50 effective full-power months.
- There are two inaccessible nuts on secondary side components (hatches, camera ports). Other nuts on these components were identified as being loose in a prior inspection. The licensee stated that it is investigating additional new/modified tooling for the two inaccessible nuts.
- In 3 of the 4 SGs, wear was identified at a tube support plate in the tube located in row 1, column 63. Although wear at the tube support plates normally tends to be random, Enclosure
the licensee did not identify any unique cause related to the wear observed on these specific tubes. Only 19 tubes were identified with wear at the tube support plates in all four SGs. The licensee plans to inspect these tubes during the next refueling outage.
Based on the review of the information provided, the NRC staff concludes that PSEG provided the information required by the Salem 2 technical specifications. 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: A. Obodoako Date: March 26, 2014
ML14010A428), PSEG Nuclear LLC (PSEG) submitted information summarizing the results of their fall 2012 steam generator (SG) tube inspections performed during the 19th refueling outage 2R19 at Salem Nuclear Generating Station, Unit 2 (Salem 2). In addition to these reports, the Nuclear Regulatory Commission (NRC) staff summarized a conference call held with PSEG, concerning the 2012 SG tube inspections, in a letter dated May 10, 2013 (ADAMS Accession No. ML13109A235).
The NRC 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 Salem 2 technical specifications and that no additional follow-up is required at this time. This completes the NRC staff efforts for Technical Assignment Control (TAC) No. MF1783.
If you have any questions regarding this matter, I may be reached at 301-415-3204 or at John. Hughey@nrc.gov.
Sincerely, Ira/
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:
Review of 2012 SG Tube Inspections cc w/encl: Distribution via Listserv DISTRIBUTION:
Public KKarwoski, NRR/DE LPL1-2 R/F RidsRgn1 MailCenter Resource AObodoako, NRR/DE RidsNrrDorllpl1-2 Resource RidsAcrsAcnw_MailCTR Resource GKulesa, NRR/DE RidsNrrLAABaxter Resource RidsNrrDeEsgb Resource MGray, Rl RidsNrrPMSalem Resource ADAMS Accession No.: ML14070A254 *by memo dated OFFICE NRR/LPL 1-2/PM NRR/LPL 1-2/LAit LPL1-2/LA ESGB/BC* LPL1-2/BC NAME JHughey KBeckford ABaxter GKluesa MKhanna DATE 03/26//2014 3/25/2014 03/26//2014 02/12/2014 03/26//2014
