ML18122A118: Difference between revisions
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| number = ML18122A118 | | number = ML18122A118 | ||
| issue date = 05/03/2018 | | issue date = 05/03/2018 | ||
| title = Review of the 2017 Steam Generator Tube Inspections During Refueling Outage 20 | | title = Review of the 2017 Steam Generator Tube Inspections During Refueling Outage 20 | ||
| author name = Lingam S | | author name = Lingam S | ||
| author affiliation = NRC/NRR/DORL/LPLIV | | author affiliation = NRC/NRR/DORL/LPLIV | ||
| addressee name = Bement R | | addressee name = Bement R | ||
| addressee affiliation = Arizona Public Service Co | | addressee affiliation = Arizona Public Service Co | ||
| docket = 05000528, 05000529, 05000530 | | docket = 05000528, 05000529, 05000530 | ||
| license number = NPF-041, NPF-051, NPF-074 | | license number = NPF-041, NPF-051, NPF-074 | ||
| contact person = Lingam S | | contact person = Lingam S, 301-415-1564 | ||
| case reference number = EPID L-2017-LRQ-0000 | | case reference number = EPID L-2017-LRQ-0000 | ||
| document type = Letter | | document type = Letter | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 3, 2018 Mr. Robert S. Bement Executive Vice President Nuclear/ Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034 | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 3, 2018 Mr. Robert S. Bement Executive Vice President Nuclear/ | ||
Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034 | |||
==SUBJECT:== | ==SUBJECT:== | ||
PALO VERDE NUCLEAR GENERATING STATION, UNIT 2-REVIEW OF THE 2017 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 20 (EPID L-2017-LRQ-OOOO) | PALO VERDE NUCLEAR GENERATING STATION, UNIT 2- REVIEW OF THE 2017 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 20 (EPID L-2017-LRQ-OOOO) | ||
==Dear Mr. Bement:== | ==Dear Mr. Bement:== | ||
By letter dated September 26, 2017 (Agencywide Documents Access and Management System Accession No. | |||
By letter dated September 26, 2017 (Agencywide Documents Access and Management System Accession No. ML17270A424), Arizona Public Service Company (the licensee) submitted information summarizing the results of the spring 2017 steam generator (SG) tube inspections performed at Palo Verde Nuclear Generating Station (PVNGS), Unit 2. These inspections were performed during spring 2017 Refueling Outage 20. The SG tube inspection report was submitted in accordance with Technical Specification (TS) 5.6.8, "Steam Generator Tube Inspection Report." | |||
The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of the submittal and concludes that the licensee provided the information required by PVNGS, Unit 2, TS 5.6.8. | |||
In addition, the NRC staff concludes that there are no technical issues that warrant followup actions at this time. A summary of the staff's review is enclosed. | |||
If you have any questions, please contact me at (301) 415-1564 or via e-mail at Siva.Lingam@nrc.gov. | If you have any questions, please contact me at (301) 415-1564 or via e-mail at Siva.Lingam@nrc.gov. | ||
Docket No. STN 50-529 | Sincerely, | ||
~(f*~ | |||
Siva P. Lingam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-529 | |||
==Enclosure:== | ==Enclosure:== | ||
Review of SG Tube Inspection Report cc: Listserv | Review of SG Tube Inspection Report cc: Listserv | ||
The tubes are supported by horizontal lattice grid supports, batwing (diagonal) supports, and vertical straps. All tube supports are constructed from Type 409 stainless steel. The licensee provided the scope, extent, methods, and results of its SG tube inspections in the letter dated September 26, 2017. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings. | |||
REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSERVICE INSPECTIONS PERFORMED DURING REFUELING OUTAGE 20 ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION, UNIT 2 DOCKET NO. STN 50-529 By letter dated September 26, 2017 (Agencywide Documents Access and Management Systems Accession No. ML17270A424), Arizona Public Service Company (the licensee) submitted information summarizing the results of the spring 2017 steam generator (SG) tube inspections performed at Palo Verde Nuclear Generating Station (PVNGS), Unit 2 during Refueling Outage (RFO) 20. The SG tube inspection report has been submitted in accordance with Technical Specification (TS) 5.6.8, "Steam Generator Tube Inspection Report." | |||
Unit 2 of PVNGS has two replacement SGs designed by Combustion Engineering and fabricated by Ansaldo Energia. Each SG has 12,580 thermally treated Alloy 690 tubes with a nominal outside diameter of 0. 750 inches and a nominal wall thickness of 0.042 inches. The tubes are arranged in a triangular pitch with 0.866-inch spacing. The tubes were hydraulically expanded at each end for the full depth of the tubesheet. The tubes are supported by horizontal lattice grid supports, batwing (diagonal) supports, and vertical straps. All tube supports are constructed from Type 409 stainless steel. | |||
The licensee provided the scope, extent, methods, and results of its SG tube inspections in the letter dated September 26, 2017. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings. | |||
After reviewing the information provided by the licensee, the U.S. Nuclear Regulatory Commission (NRC) staff has the following comment and observation: | After reviewing the information provided by the licensee, the U.S. Nuclear Regulatory Commission (NRC) staff has the following comment and observation: | ||
* The licensee performed an inspection of the blowdown patch plate welds in SGs 21 and 22 that were found to be cracked during RFO 15. The inspections confirmed that the weld material in the vicinity of the cracked weld on all 4 patch plates is intact and a loose parts concern is not being created. Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by PVNGS, Unit 2, TS 5.6.8. In addition, the staff concludes that 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. Enclosure | * The licensee performed an inspection of the blowdown patch plate welds in SGs 21 and 22 that were found to be cracked during RFO 15. The inspections confirmed that the weld material in the vicinity of the cracked weld on all 4 patch plates is intact and a loose parts concern is not being created. | ||
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by PVNGS, Unit 2, TS 5.6.8. In addition, the staff concludes that 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. | |||
Enclosure | |||
ML18122A118 *SE memorandum dated OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DMLR/MCCB/BC* NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME SLingam PBlechman SBloom RPascarelli SLingam DATE 5/3/18 5/3/18 4/30/18 5/3/18 5/3/18}} | |||
NRR/DORL/LPL4/ | |||
Latest revision as of 07:04, 21 October 2019
| ML18122A118 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/03/2018 |
| From: | Siva Lingam Plant Licensing Branch IV |
| To: | Bement R Arizona Public Service Co |
| Lingam S, 301-415-1564 | |
| References | |
| EPID L-2017-LRQ-0000 | |
| Download: ML18122A118 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 3, 2018 Mr. Robert S. Bement Executive Vice President Nuclear/
Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNIT 2- REVIEW OF THE 2017 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 20 (EPID L-2017-LRQ-OOOO)
Dear Mr. Bement:
By letter dated September 26, 2017 (Agencywide Documents Access and Management System Accession No. ML17270A424), Arizona Public Service Company (the licensee) submitted information summarizing the results of the spring 2017 steam generator (SG) tube inspections performed at Palo Verde Nuclear Generating Station (PVNGS), Unit 2. These inspections were performed during spring 2017 Refueling Outage 20. The SG tube inspection report was submitted in accordance with Technical Specification (TS) 5.6.8, "Steam Generator Tube Inspection Report."
The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of the submittal and concludes that the licensee provided the information required by PVNGS, Unit 2, TS 5.6.8.
In addition, the NRC staff concludes that there are no technical issues that warrant followup actions at this time. A summary of the staff's review is enclosed.
If you have any questions, please contact me at (301) 415-1564 or via e-mail at Siva.Lingam@nrc.gov.
Sincerely,
~(f*~
Siva P. Lingam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-529
Enclosure:
Review of SG Tube Inspection Report cc: Listserv
REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSERVICE INSPECTIONS PERFORMED DURING REFUELING OUTAGE 20 ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION, UNIT 2 DOCKET NO. STN 50-529 By letter dated September 26, 2017 (Agencywide Documents Access and Management Systems Accession No. ML17270A424), Arizona Public Service Company (the licensee) submitted information summarizing the results of the spring 2017 steam generator (SG) tube inspections performed at Palo Verde Nuclear Generating Station (PVNGS), Unit 2 during Refueling Outage (RFO) 20. The SG tube inspection report has been submitted in accordance with Technical Specification (TS) 5.6.8, "Steam Generator Tube Inspection Report."
Unit 2 of PVNGS has two replacement SGs designed by Combustion Engineering and fabricated by Ansaldo Energia. Each SG has 12,580 thermally treated Alloy 690 tubes with a nominal outside diameter of 0. 750 inches and a nominal wall thickness of 0.042 inches. The tubes are arranged in a triangular pitch with 0.866-inch spacing. The tubes were hydraulically expanded at each end for the full depth of the tubesheet. The tubes are supported by horizontal lattice grid supports, batwing (diagonal) supports, and vertical straps. All tube supports are constructed from Type 409 stainless steel.
The licensee provided the scope, extent, methods, and results of its SG tube inspections in the letter dated September 26, 2017. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings.
After reviewing the information provided by the licensee, the U.S. Nuclear Regulatory Commission (NRC) staff has the following comment and observation:
- The licensee performed an inspection of the blowdown patch plate welds in SGs 21 and 22 that were found to be cracked during RFO 15. The inspections confirmed that the weld material in the vicinity of the cracked weld on all 4 patch plates is intact and a loose parts concern is not being created.
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by PVNGS, Unit 2, TS 5.6.8. In addition, the staff concludes that 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.
Enclosure
ML18122A118 *SE memorandum dated OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DMLR/MCCB/BC* NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME SLingam PBlechman SBloom RPascarelli SLingam DATE 5/3/18 5/3/18 4/30/18 5/3/18 5/3/18