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| number = ML18092A032
| number = ML18092A032
| issue date = 04/09/2018
| issue date = 04/09/2018
| title = St. Lucie Nuclear Plant, Unit 2 - Steam Generator Tube Inspection Report Review (EPID L-2017-LRO-0080)
| title = Steam Generator Tube Inspection Report Review
| author name = Buckberg P H
| author name = Buckberg P
| author affiliation = NRC/NRR/DORL/LPLII-2
| author affiliation = NRC/NRR/DORL/LPLII-2
| addressee name = Nazar M
| addressee name = Nazar M
Line 9: Line 9:
| docket = 05000389
| docket = 05000389
| license number = NPF-016
| license number = NPF-016
| contact person = Buckberg P H, NRR/DORL/LPL2-2, 415-1447
| contact person = Buckberg P, NRR/DORL/LPL2-2, 415-1447
| case reference number = EPID L-2017-LRO-0080
| case reference number = EPID L-2017-LRO-0080
| document type = Inspection Report, Letter
| document type = Inspection Report, Letter
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division Florida Power & Light Company Mail Stop EX/JB 700 Universe Blvd. Juno Beach, FL 33408 April 9, 2018
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 9, 2018 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division Florida Power & Light Company Mail Stop EX/JB 700 Universe Blvd.
Juno Beach, FL 33408


==SUBJECT:==
==SUBJECT:==
ST. LUCIE PLANT UNIT NO. 2 -REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT FOR REFUELING OUTAGE 23 (EPID L-2017-LR0-0080)  
ST. LUCIE PLANT UNIT NO. 2 - REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT FOR REFUELING OUTAGE 23 (EPID L-2017-LR0-0080)


==Dear Mr. Nazar:==
==Dear Mr. Nazar:==
By letter dated September 13, 2017 (Agencywide Documents Access and Management System Accession No. ML 17257A080), Florida Power and Light Company submitted a report of the spring 2017 steam generator tube inspections performed at St. Lucie Plant Unit No. 2. These inspections were performed during Refueling Outage 23 in accordance with Technical Specification (TS) Section 6.8.4.1. The Nuclear Regulatory Commission (NRC) staff has completed its review of the report provided, concludes that the licensee provided the information required by their TSs, and that no additional followup is required at this time. The NRC staff's review of the report is enclosed.
 
Docket No. 50-389  
By letter dated September 13, 2017 (Agencywide Documents Access and Management System Accession No. ML17257A080), Florida Power and Light Company submitted a report of the spring 2017 steam generator tube inspections performed at St. Lucie Plant Unit No. 2. These inspections were performed during Refueling Outage 23 in accordance with Technical Specification (TS) Section 6.8.4.1.
The Nuclear Regulatory Commission (NRC) staff has completed its review of the report provided, concludes that the licensee provided the information required by their TSs, and that no additional followup is required at this time. The NRC staff's review of the report is enclosed.
Sincerely,
                                                          /./?  /
                                                  -~:/;:?. ;;/'_
                                                  /:j:Y$1 Perry ~kberg, Senior Project Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389


==Enclosure:==
==Enclosure:==


As stated cc: ListServ Sincerely, /./? / -~:/;:?. ;;/' __ /:j:Y$1 Perry ~kberg, Senior Project Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT ST. LUCIE PLANT UNIT NO. 2 DOCKET NO. 50-389 EPID L-2017-LR0-0080 By letter dated September 13, 2017 (Agencywide Documents Access and Management System Accession No. ML 17257A080), Florida Power & Light Company (the licensee) submitted the results of the steam generator (SG) inspections performed at St. Lucie Plant Unit No. 2 during the twenty-third refueling outage (RFO 23). St. Lucie Plant Unit No. 2 has two Model 86/19TI replacement SGs that were manufactured by AREVA and installed in 2007. Each SG has 8,999 thermally treated Alloy 690 tubes with a nominal outside diameter of 0.75 inches and a nominal wall thickness of 0.043 inches. During manufacturing, all tubes were hydraulically expanded at both ends over the full depth of the tubesheet.
As stated cc: ListServ
The tubesheet was drilled on a triangular pitch with 1.0-inch spacing, center-to-center.
 
The radius of the row 1 U-bends is 4.134 inches. The U-bends in rows 1 through 15 were stress relieved after bending. Seven Type 410 Stainless Steel tube support plates, each 1.181 inches thick with broached trefoil holes, support the vertical section of the tubes. Four sets of anti-vibration bars (AVBs), each 0.112 inches thick and made from Type 405 Stainless Steel, support the U-bend section of the tubes. The licensee provided the scope, extent, methods, and results of their SG tube inspections in the September 13, 2017, inspections report. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the inspection findings.
REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT ST. LUCIE PLANT UNIT NO. 2 DOCKET NO. 50-389 EPID L-2017-LR0-0080 By letter dated September 13, 2017 (Agencywide Documents Access and Management System Accession No. ML17257A080), Florida Power & Light Company (the licensee) submitted the results of the steam generator (SG) inspections performed at St. Lucie Plant Unit No. 2 during the twenty-third refueling outage (RFO 23).
St. Lucie Plant Unit No. 2 has two Model 86/19TI replacement SGs that were manufactured by AREVA and installed in 2007. Each SG has 8,999 thermally treated Alloy 690 tubes with a nominal outside diameter of 0.75 inches and a nominal wall thickness of 0.043 inches. During manufacturing, all tubes were hydraulically expanded at both ends over the full depth of the tubesheet. The tubesheet was drilled on a triangular pitch with 1.0-inch spacing, center-to-center. The radius of the row 1 U-bends is 4.134 inches. The U-bends in rows 1 through 15 were stress relieved after bending. Seven Type 410 Stainless Steel tube support plates, each 1.181 inches thick with broached trefoil holes, support the vertical section of the tubes. Four sets of anti-vibration bars (AVBs), each 0.112 inches thick and made from Type 405 Stainless Steel, support the U-bend section of the tubes.
The licensee provided the scope, extent, methods, and results of their SG tube inspections in the September 13, 2017, inspections report. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the inspection findings.
Based on its review of the report submitted, the staff has the following observations and comments:
Based on its review of the report submitted, the staff has the following observations and comments:
* A visual inspection of the upper internals section of both SGs, including the feedwater rings and supports, showed no damage or deficiencies.
* A visual inspection of the upper internals section of both SGs, including the feedwater rings and supports, showed no damage or deficiencies.
* Tube wear, located at the u-bend apex due to interaction with AVBs, was detected using the bobbin probe on some tubes in row 69 of both SGs, and one tube in row 40 of SG 2A. Row 69 and row 40 are located just below the AVB 4/5 and AVB 3/6 design depth locations, respectively.
* Tube wear, located at the u-bend apex due to interaction with AVBs, was detected using the bobbin probe on some tubes in row 69 of both SGs, and one tube in row 40 of SG 2A. Row 69 and row 40 are located just below the AVB 4/5 and AVB 3/6 design depth locations, respectively. Prior to the RFO 23 inspection, u-bend apex wear had only been identified in row 69 tubes. The deepest u-bend apex wear indication was 33-percent through-wall depth (TWO) in SG 2A and 9 percent TWO in SG 28, both in row 69. The highest growth rate of previously-identified u-bend apex wear indications was 4 percent TWO, since the previous inspection in RFO 22. The u-bend apex wear indication at the AVB 3/6 location in SG 2A measured 6 percent TWO.
Prior to the RFO 23 inspection, u-bend apex wear had only been identified in row 69 tubes. The deepest u-bend apex wear indication was 33-percent through-wall depth (TWO) in SG 2A and 9 percent TWO in SG 28, both in row 69. The highest growth rate of previously-identified u-bend apex wear indications was 4 percent TWO, since the previous inspection in RFO 22. The u-bend apex wear indication at the AVB 3/6 location in SG 2A measured 6 percent TWO. Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by their technical specifications.
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by their technical specifications. In addition, the staff concludes there are no technical issues that warrant followup 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. Although the number of wear indications is greater than the number of wear indications found at other AREVA SGs of similar age, the depths of these indications (i.e., the severity) are comparable to those observed at other plants.
In addition, the staff concludes there are no technical issues that warrant followup 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. Although the number of wear indications is greater than the number of wear indications found at other AREVA SGs of similar age, the depths of these indications (i.e., the severity) are comparable to those observed at other plants. Enclosure
Enclosure


==SUBJECT:==
==SUBJECT:==
ST. LUCIE PLANT UNIT NO. 2 -REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT FOR REFUELING OUTAGE 23 (EPID L-2017-LR0-0080)
ST. LUCIE PLANT UNIT NO. 2 - REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT FOR REFUELING OUTAGE 23 (EPID L-2017-LR0-0080) DATED APRIL 9, 2018 DISTRIBUTION:
DATED APRIL 9, 2018 DISTRIBUTION:
PUBLIC RidsNrrDorl RidsNrrDorlLpl2-2 RidsNrrDmlrMccb RidsACRS_MailCTR RidsNrrPMStLucie RidsRgn2MailCenter RidsNrrLABClayton RidsNrrDlmrMccb PKlein, NRR AJohnson, NRR AHuyn, NRR ADAMS Access1on N0. ML18092A032                    *bv memorandum OFFICE     D0RL/LPL2-2/PM D0RL/LPL2-2/LA DMLR/MCCB/BC* LPL2-2/BC(A) D0RL/LPL2-2/PM NAME       PBuckberg     BClayton       SBloom         BTindell   PBuckberg DATE       04/04/2018     04/03/2018     03/15/2018     04/06/2018 04/09/2018 OFFICIAL RECORD COPY}}
PUBLIC RidsNrrDorl RidsNrrDorlLpl2-2 RidsNrrDmlrMccb RidsACRS_MailCTR RidsNrrPMStLucie  
 
RidsRgn2MailCenter RidsNrrLABClayton RidsNrrDlmrMccb PKlein, NRR AJohnson, NRR AHuyn, NRR ADAMS A ccess1on N ML18092 0. A032 *bv memorandum OFFICE D0RL/LPL2-2/PM D0RL/LPL2-2/LA DMLR/MCCB/BC*
LPL2-2/BC(A)
NAME PBuckberg BClayton SBloom BTindell DATE 04/04/2018 04/03/2018 03/15/2018 04/06/2018 OFFICIAL RECORD COPY D0RL/LPL2-2/PM PBuckberg 04/09/2018}}

Latest revision as of 12:23, 21 October 2019

Steam Generator Tube Inspection Report Review
ML18092A032
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 04/09/2018
From: Perry Buckberg
Plant Licensing Branch II
To: Nazar M
NextEra Energy
Buckberg P, NRR/DORL/LPL2-2, 415-1447
References
EPID L-2017-LRO-0080
Download: ML18092A032 (3)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 9, 2018 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division Florida Power & Light Company Mail Stop EX/JB 700 Universe Blvd.

Juno Beach, FL 33408

SUBJECT:

ST. LUCIE PLANT UNIT NO. 2 - REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT FOR REFUELING OUTAGE 23 (EPID L-2017-LR0-0080)

Dear Mr. Nazar:

By letter dated September 13, 2017 (Agencywide Documents Access and Management System Accession No. ML17257A080), Florida Power and Light Company submitted a report of the spring 2017 steam generator tube inspections performed at St. Lucie Plant Unit No. 2. These inspections were performed during Refueling Outage 23 in accordance with Technical Specification (TS) Section 6.8.4.1.

The Nuclear Regulatory Commission (NRC) staff has completed its review of the report provided, concludes that the licensee provided the information required by their TSs, and that no additional followup is required at this time. The NRC staff's review of the report is enclosed.

Sincerely,

/./? /

-~:/;:?. ;;/'_

/:j:Y$1 Perry ~kberg, Senior Project Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389

Enclosure:

As stated cc: ListServ

REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT ST. LUCIE PLANT UNIT NO. 2 DOCKET NO. 50-389 EPID L-2017-LR0-0080 By letter dated September 13, 2017 (Agencywide Documents Access and Management System Accession No. ML17257A080), Florida Power & Light Company (the licensee) submitted the results of the steam generator (SG) inspections performed at St. Lucie Plant Unit No. 2 during the twenty-third refueling outage (RFO 23).

St. Lucie Plant Unit No. 2 has two Model 86/19TI replacement SGs that were manufactured by AREVA and installed in 2007. Each SG has 8,999 thermally treated Alloy 690 tubes with a nominal outside diameter of 0.75 inches and a nominal wall thickness of 0.043 inches. During manufacturing, all tubes were hydraulically expanded at both ends over the full depth of the tubesheet. The tubesheet was drilled on a triangular pitch with 1.0-inch spacing, center-to-center. The radius of the row 1 U-bends is 4.134 inches. The U-bends in rows 1 through 15 were stress relieved after bending. Seven Type 410 Stainless Steel tube support plates, each 1.181 inches thick with broached trefoil holes, support the vertical section of the tubes. Four sets of anti-vibration bars (AVBs), each 0.112 inches thick and made from Type 405 Stainless Steel, support the U-bend section of the tubes.

The licensee provided the scope, extent, methods, and results of their SG tube inspections in the September 13, 2017, inspections report. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the inspection findings.

Based on its review of the report submitted, the staff has the following observations and comments:

  • A visual inspection of the upper internals section of both SGs, including the feedwater rings and supports, showed no damage or deficiencies.
  • Tube wear, located at the u-bend apex due to interaction with AVBs, was detected using the bobbin probe on some tubes in row 69 of both SGs, and one tube in row 40 of SG 2A. Row 69 and row 40 are located just below the AVB 4/5 and AVB 3/6 design depth locations, respectively. Prior to the RFO 23 inspection, u-bend apex wear had only been identified in row 69 tubes. The deepest u-bend apex wear indication was 33-percent through-wall depth (TWO) in SG 2A and 9 percent TWO in SG 28, both in row 69. The highest growth rate of previously-identified u-bend apex wear indications was 4 percent TWO, since the previous inspection in RFO 22. The u-bend apex wear indication at the AVB 3/6 location in SG 2A measured 6 percent TWO.

Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by their technical specifications. In addition, the staff concludes there are no technical issues that warrant followup 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. Although the number of wear indications is greater than the number of wear indications found at other AREVA SGs of similar age, the depths of these indications (i.e., the severity) are comparable to those observed at other plants.

Enclosure

SUBJECT:

ST. LUCIE PLANT UNIT NO. 2 - REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT FOR REFUELING OUTAGE 23 (EPID L-2017-LR0-0080) DATED APRIL 9, 2018 DISTRIBUTION:

PUBLIC RidsNrrDorl RidsNrrDorlLpl2-2 RidsNrrDmlrMccb RidsACRS_MailCTR RidsNrrPMStLucie RidsRgn2MailCenter RidsNrrLABClayton RidsNrrDlmrMccb PKlein, NRR AJohnson, NRR AHuyn, NRR ADAMS Access1on N0. ML18092A032 *bv memorandum OFFICE D0RL/LPL2-2/PM D0RL/LPL2-2/LA DMLR/MCCB/BC* LPL2-2/BC(A) D0RL/LPL2-2/PM NAME PBuckberg BClayton SBloom BTindell PBuckberg DATE 04/04/2018 04/03/2018 03/15/2018 04/06/2018 04/09/2018 OFFICIAL RECORD COPY

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